OFFICE OF CIVILIAN RADIOACTIVE WASTE MANAGEMENT I. CIA: …/67531/metadc739081/m2/1/high_re… ·...

OFFICE OF CIVILIAN RADIOACTIVE WASTE MANAGEMENT I . CIA: QA Page: 1 of: 1 SPECIAL INSTRUCTION SHEET

Complete Only Applicable Items

This is a placeholder page for records that cannot be scanned. I 3. Accession Number 2. Record Date

2 ~ / i 7/23 O Z d 3 0711 910 1

4. Author Name@) 5. Author Organization SCHEIDER, A. I NIA

I

6. TitldDescription THERMAL EVALUATION OF THE FORT SAINT VRAIN CODISPOSAL WASTE PACKAGE

7. Document Number(s) 8. Version Designator CAL-WIS-TH-000012 REV 00

9. Document Type 10. Medium DESIGN DOCUMENT OPTICJPAPER

I

11. Access Cantrd Code PUB

12. Traceability Designator #CAL-WIS-TH-000012

13. Comments THIS ONE OF A KIND COLOR GRAPHIC DOCUMENT CAN BE LOCATED THRU THE RECORDS PROCESSING CENTER

MOL.20010718.0263

OFFICE OF CIVILIAN RADIOACTIVE WASTE MANAGEMENT 1, QA: QA

CALCULATION COVER SHEET Page:l Of: I - - . .

!. Calculation Title rhermal Evaluation of the Fort Saint Vrain Codisposal Waste Package

,AL-WIS-TH-OOOb 12 REV 00

2. Total Attachments

Document Identifier includin Revision Number)

~

I 5 Attachment Numbers - Number of Daaes in each 5 I I on CD (Compact Disc), 11-2, 111-2, IV-3, V-4

I Print Name I Signature

7. Checker Hongyan Marr/Halim Alsaed

3. Lead as Michael Anderson

Horia Radulescu is the author of Attachment V only. / Halim Alsaed is the checker of Attachment V only.

Bate

I O . Revision No.

00

P-3.12Q.1

Revision History

11. Description of Revision

Initial Issuance.

Rev. 06/30/199

b

Page

Waste Package Proiect Calculation Title: Thermal Evaluation of the Fort Saint Vrain Codisposal Waste Package Document Identifier: CAL- WIS-TH-0000 12 REV 00 Page 2 of 28

CONTENTS

1 . PURPOSE .................................................................................................................................. 4

2 . METHOD .................................................................................................................................. 4

3 . ASSUMPTIONS ........................................................................................................................ 4

4 . USE OF COMPUTER SOFTWARE AND CONTROLS ......................................................... 6

5 . CALCULATION ....................................................................................................................... 7 5.1 Thermal Properties ............................................................................................................... 7 5.2 Finite Element Representation ............................................................................................ 14 5.3 Heat Load and Boundary Conditions ................................................................................. 15

. .

6 . RESULTS ................................................................................................................................ 19

7 . REFERENCES ........................................................................................................................ 26

8 . ATTACHMENTS .................................................................................................................... 28

FIGURES

Page

6.1 . FEA Mesh #I ........................................................................................................................ 19

6-2 . Maximum Temperatures from Mesh #1 ............................................................................... 20

6-3 . Temperature vs . Time at outer surface ofHexagona1 Block ................................................ 21

6-4 . Temperature vs . Time for DHLW glass ............................................................................... 22

6-5 . FSV Fuel Block Mesh .......................................................................................................... 23

6-6 . Max Temperatures in the FSV Fuel Block ........................................................................... 24

6-7 . Temp vs Time for the Bounding Nodes ............................................................................... 25

Waste Package Proiect Calculation Title: Thermal Evaluation of the Fort Saint Vrain Codisposal Waste Package Document Identifier: CAL-WIS-TH-000012 REV 00 Page 3 of 28

TABLES

Page

5.1-1. Waste Package Materials ..................................................................................................... 7

5.1-2. Material Properties for SS 3 16, 3 16L, and 3 16NG ............................................................. 8

5.1-3. Material Properties for SS 304L .......................................................................................... 9

5.1-4. Material Properties for SA-5 16 ......................................................................................... 10

5.1-5. Specific Heat of FSV Graphite Block ............................................................................... 11

5.1-6. Thermal Conductivity of FSV Graphite Block .................................................................. 12

5.1-7. Thermal Conductivity and Specific Heat of Alloy 22 ....................................................... 13

5.1-9. Thermal Conductivity and Specific Heat of Air ................................................................ 14

5.3-1. Heat Generation of DHLW Glass ...................................................................................... 16

5.3-2. Heat Generation of FSV Fuel ............................................................................................ 17

5.3-3. WP Boundary Conditions .................................................................................................. 18

8-1 . List of Attachments Submitted in the Form of Electronic Files in Attachment I .................. 28

Waste Package Pro-iect Calculation Title: Thermal Evaluation of the Fort Saint Vrain Codisposal Waste Package Document Identifier: CAL-WIS-TH-0000 12 REV 00 Page 4 of 28

1. PURPOSE

The objective of this calculation is to evaluate the thermal response of the Fort Saint Vrain (FSV) Codisoposal Waste Package (WP) design under nominal Monitored Geologic Repository conditions. The objective of the calculation is to provide thermal parameter information to support the FSV waste package design. The information provided by the sketches (Attachment IV) is that of the potential design of the type of WP considered in this calculation, and all obtained results are valid for that design only. This calculation is associated with the WP design and was performed by the Waste Package Design group in accordance with the Technical Work Plan for: Waste Package Design Description for LA (Ref. 16). AP-3.124, Calculations (Ref. 17) is used to perform the calculation and develop the document. The sketches attached to this calculation provide the potential dimensions and materials for the SDHLW (Defense High Level Waste) / DOE (Department of Energy) Long WP.

2. METHOD

The solution method employed is a two-dimensional (2D) finite element analysis. The calculation uses WP emplacement thermal evaluation results (Ref. 10) for the WP surface temperatures as the boundary condition, and applies the heat loads in the DHLW glass and FSV fuel to determine the temperatures in the WP. The temperature calculation is performed under transient conditions after emplacement of the WP in the repository.

Due to the highly complex geometry of the FSV fuel, two separate representations will be used. The first will be a half symmetry representation of the WP with a distributed representation of the FSV fuel. The second will be a half symmetry representation of the FSV fuel, complete with vent holes and fuel compact holes, with applied boundary conditions (temperatures) from the first representation. This will allow for an accurate representation of the problem and simultaneously give faster computation time than would be expected from a single, large representation.

The finite element calculation was performed by using the commercially available ANSYS Version (V) 5.6.2 (Software Tracking Number [STN] 10364-5.6.2-00; Ref. 3). With regard to the development of this calculation, the control of electronic management of data was evaluated in accordance with AP-SV. 1 Q, Control of the Electronic Management of Information (Ref. 19) and the Technical Work Plan (Ref. 16). The evaluation (Addendum B of Ref. 16) determined that current work processes and procedures are adequate for the control of the electronic management of data for this activity.

3. ASSUMPTIONS

In the course of developing this document, the following assumptions are made regarding the thermal calculation.

I

3.1 The Hanford Long glass canister is assumed for the glass canister design, and is assumed to have an age of zero. The rationale is that there is no criterion for minimum aging time


of the DHLW. This assumption may result in conservative temperature results. This assumption is used in Section 5.3.

3.2 It is assumed that a 2D finite element representation of a cross section of the waste package will be representative of the hottest portion of the WP. The rationale for this assumption is that axial heat transfer does not significantly affect the solution (Le., the flow of heat in the radial direction is assumed to dominate the solution). This assumption is used in Section 5.2.

3.3 The thermal conductivity of helium at atmospheric pressure is assumed to be representative of the conditions which helium in the WP will experience. The rationale of this assumption is the fact that one atmosphere fill pressure at ambient temperature is representative of the industry standard for storage casks. Page 10 of Ref. 13 states the highest pressure to which storage casks may be filled is approximately 1.5 atmospheres. Also, most industry vendors use substantially lower pressure in their designs. Although the internal pressure of the WP will increase due to the temperature rise, according to p. 255, Ref. 5 , the thermal conductivity of most gasses is pressure independent. Thus, using the thermal conductivity at atmospheric pressure is reasonable. This assumption is used in Section 5.1.

3.4 Modeling of only conduction and radiation heat transfer is assumed to provide conservative results for this calculation. The rationale for this assumption is as follows: the fill gas in the WP will allow a convective heat transfer path to exist; however, the natural convective heat transfer will have a small or negligible impact on the total heat transfer. Attachment X, Ref. 4, estimates the effect of the convective heat transfer inside the 5-DHLW WP. The analysis indicates a potential for convection cells to develop in the larger cavities near the top and sides of the WP internals. Convection will likely not play a role in transferring heat near the bottom of the WP where heat transfer will be clearly dominated by conduction and thermal radiation. The total impact of convection on heat transfer within the WP is estimated to be less than 10%. Thus, the problem may be modeled with only the dominant heat transfer modes with a slightly conservative impact upon the results. This assumption is used in Section 5.2.

3.5 Reference 6 provides equations to calculate the thermal conductivity (k) of the graphite block. These equations are dependent upon whether the graphite is irradiated or unirradiated. This calculation will consider the unirradiated case only. The rationale for this assumption is that Ref. 6 did not provide complete information to solve for the irradiated case. The only choice was to use the unirradiated equations. This assumption is used in Section 5.1.

3.6 The volume of glass contained in the Hanford Long canister is undetermined. This is due to the fact that none of these canisters have been made yet. The volume of glass inside these canisters is assumed to be 1.08 m3. The rationale for this assumption is that this number is found in Table RL-3 in Ref. 12. The difference between this value and the actual value is anticipated to have a negligible effect on any results reported in this calculation. This assumption is used in Section 5.3.


3.7

3.8

3.9

The thermal material properties, except thermal conductivity, of borosillicate glass are not found in a source that may be referenced. Therefore, the properties of pyrex glass will be used from Reference 2 in Table A.3 of Appendix A. The rationale for this assumption is that pyrex and borosillicate glass are similar and the differences in their thermal properties is anticipated to be negligible. This Assumption is used in Section 5.1.

The emissivity of Nickel Alloy will be assumed for Alloy 22. This rationale for this assumption is that Alloy 22 is a Nickel Alloy and therefore has similar chemical composition. Reference 14 lists the emissivity of Nickel Alloy. The impact on the results is considered to be negligible. This assumption is used in Section 5.1.

The fill gas used in the DOE SNF (Spent Nuclear Fuel) Canister is assumed to be air. The rationale for this assumption is that Ref. 6 does not provide any information that the fill gas would not be air. If a special fill gas was used, it should be mentioned in Ref. 6. Since no alternate gas is mentioned, it is reasonable to assume the fill gas to be air. This assumption is used in Section 5.1.

4. USE OF COMPUTER SOFTWARE AND CONTROLS

The finite element analysis (FEA) computer code used for this calculation is ANSYS V5.6.2 (Ref. 3), which is identified with the Software Tracking number (STN) 10364-5.6.2-00 and was obtained from Software Configuration Management in accordance with appropriate procedures (Ref. 18). ANSYS V5.6.2 is a qualified commercially available finite element analysis code and is appropriate for thermal calculations of WPs as performed in this calculation. The calculations using the ANSYS V5.6.2 software were executed on a Hewlett-Packard (HP) 9000 Series UNIX workstation, Yucca Mountain Project (YMP) tag number 7003 14 located in Las Vegas, NV. The ANSYS evaluations performed for these designs are fully within the range of the validation performed for the ANSYS V5.6.2 code. Access to the code was granted by the Software Configuration Secretariat in accordance with the appropriate procedures. ANSYS V5.6.2 was used for pre- and post-processing.

The FEA computer code used for executing the solution was ANSYS V5.4 (Ref. 22), which is identified with the Computer Software Configuration Item (CSCI) 30040 V5.4 and was obtained from Software Configuration Management in accordance with the appropriate procedures (Ref. 18). ANSYS V5.4 is a qualified commercially available finite element analysis code and is appropriate for thermal calculations as performed in this calculation. The calculations using the ANSYS V5.4 software were executed on a Hewlett-Packard (HP) UNIX workstation, YMP tag number 7003 14 located in Las Vegas, Nevada. The ANSYS evaluations performed for these designs are fully within the range of the validation performed for the ANSYS V5.4 code. Software Configuration Management, in accordance with the appropriate procedures, granted access to the code.

The input files may be found at the beginning of the output files provided in Attachment I and are listed in Table 8-1.

Waste Package Project Calculation Title: Thermal Evaluation of the Fort Saint Vrain Codisposal Waste Package Document Identifier: CAL-WIS-TH-0000 12 REV 00

5. CALCULATION

5.1 Thermal Properties

Table 5.1-1 lists the materials used in the FSV Codisposal WP.

Table 5.1-1. Waste Package Materials

Page 7 of 28

Table 5.1-2 lists the material properties for SS 3 16, 3 16L, and 3 16NG. The material properties are the same since they are in the same material grouping (Table TCD, Ref. 1, Section 11, Part D). The properties in SI units are converted from English units supplied in the ASME (American Society of Mechanical Engineers) (Ref. 1, Table TCD). It should be noted that the thermal diffusivity is represented by the symbol a.

SA-240 S3 1600 (3 16NG SS, which is 3 16 SS with tightened control on carbon and nitrogen content and has the same material properties as 316 SS [see Ref. 27, page 931 and Ref. 1, Section 11, SA-240 Table 11) (inner shell) is the correct designation for both SS 316NG and SS 316.

Waste Packape Proiect Calculation Title: Thermal Evaluation of the Fort Saint Vrain Codisposal Waste Package Document Identifier: CAL-WIS-TH-000012 REV 00

Temp ( O F )

70 100 150 200 250 300 350 400 450 500 550 600 650 700 750 800 850 900 950 1000

1350 1400 1450 1500

050 100 150 200 250 300

Table 5.1-2. Material Properties for SS 316, 31 6L, and 31 6NG

k (Btulhr-ft-OF) 8.2 8.3 8.6 8.8 9.1 9.3 9.5 9.8 10.0 10.2 10.5 10.7 10.9 11.2 11.4 1.6 1.9 2.1 2.3 2.5 2.8

13.0 13.2 13.4 13.6 13.8 14.1 14.3 14.5 14.7

k (Wlm-K) 14.2 14.4 14.9 15.2 15.7 16.1 16.4 17..0 17.3 17.7 18.2 18.5 18.9 19.4 19.7 20.1 20.6 20.9 21.3 21.6 22.2 22.5 22.8 23.2 23.5 23.9 24.4 24.7 25.1 25.4

Temp ("C) 21 38 66 93 121 149 177 204 232 260 288 316 343 371 399 427 454 482 510 538 566 593 62 1 649 677 704 732 760 788 816

a (ft21hr) 0.139 0.140 0.142 0.145 0.147 0.150 0.152 0.155 0.157 0.160 0.162 0.165 0.167 0.170 0.172 0.175 0.177 0.179 0.182 0.184 0.187 0.189 0.191 0.194 0.196 0.198 0.200 0.202 0.205 0.207

Cp (Btullb-OF) 0.118 0.1 19 0.122 0.122 0.124 0.124 0.126 0.127 0.128 0.128 0.130 0.130 0.131 0.132 0.133 0.133 0.135 0.136 0.136 0.136 0.137 0.138 0.139 0.139 0.139 0.140 0.142 0.1422 0.1420 0.143

Page 8 of 28

Cp (Jlkg-K) 495.9 498.4 509.1 510.2 520.4 521.2 525.4 531.5 535.5 535.9 544.9 545.2 548.7 553.9 557.2 557.2 565.2 568.3 568.1 571 .I 575.4 578.2 581 .O 580.7 583.3 585.9 592.7 595.1 594.6 597.0

The emissivity of SS 316, SS 316L, and SS 316NG is 0.62, which is the median of the values given in Reference 21, Table 4.3.2.

The density of SS 3 16, SS 3 16L, and SS 3 16NG is 7.98 g/cm3 (Ref. 8, Appendix Xl).

Table 5.1-3 lists the material properties for SS 304L. The properties in SI units are converted from English units supplied in the ASME (Ref. 1, Table TCD).

Waste Packape Proiect Calculation Title: Thermal Evaluation of the Fort Saint Vrain Codisposal Waste Package Document Identifier: CAL-WIS-TH-0000 12 REV 00 Page 9 of 28

Table 5.1-3. Material Properties for SS 304L

Temp ("F) 70 100 1 50 200 250 300 350 400 450 500 550 600 650 700 750 800 850 900 950 1000 1050 1100 1150 1200 1250 1300 1350 1400 1450 1500

k (Btulhr-ft-"F) k (Wlm-K) 8.6 14.9 8.7 15.1 9.0 15.6 9.3 16.1 9.6 16.6 9.8 17.0 10.1 17.5 10.4 18.0 10.6 18.3 10.9 18.9 11.1 19.2 11.3 19.6 11.6 20.1 11.8 20.4 12.0 20.8 12.2 21 .I 12.5 21.6 12.7 22.0 12.9 22.3 13.2 22.8 13.4 23.2 13.6 23.5 13.8 23.9 14.0 24.2 14.3 24.7 14.5 25.1 14.7 25.4 14.9 25.8 15.1 26.1 15.3 26.5

Temp ("C) 21 38 66 93 121 149 177 204 232 260 288 316 343 371 399 427 454 482 51 0 538 566 593 621 649 677 704 732 760 788 816

a (ft*lhr) 0.151 0.152 0.1 54 0.156 0.158 0.160 0.162 0.165 0.167 0.170 0.172 0.174 0.177 0.179 0.181 0.184 0.186 0.189 0.191 0.194 0.196 0.198 0.201 0.203 0.205 0.208 0.21 0 0.212 0.214 0.216

Cp (Btullb-OF) 0.115 0.115 0.118 0.120 0.122 0.123 0.126 0.127 0.128 0.129 0.130 0.131 0.132 0.133 0.134 0.134 0.135 0.135 0.136 0.137 0.138 0.138 0.138 0.139 0.141 0.141 0.141 0.142 0.142 0.143

Cp (Jlkg-K) 480.7 483.1 493.3 503.2 512.8 517.0 526.2 532.0 535.8 541.2 544.7 548.2 553.2 556.4 559.6 559.7 567.2 567.2 570.1 574.3 577.1 579.8 579.5 582.1 588.8 588.4 590.8 593.2 595.6 597.9

The emissivity of SS 304L is 0.73, which is the median of the values given in Reference 21, Table 4.3.2.

The density of SS 304L is 7.94 g/cm3 (Ref. 8, Appendix Xl).

Table 5.1-4 lists the material properties for SA-5 16. The properties in SI units are converted from English units supplied in the ASME (Ref. 1 , Table TCD).

Waste Package Pro-iect Calculation Title: Thermal Evaluation of the Fort Saint Vrain Codisposal Waste Package Document Identifier: CAL-WIS-TH-0000 12 REV 00

Temp (OF) 70 100 150 200 250 300 350 400 450 500 550 600 650 700 750 800 850 900 950 1000 1050 1100 1150 1200 1250 1300 1350 1400 1450 1500

Table 5.1-4. Material Properties for SA-516

k (Btulhr-ft-OF) 27.5 27.6 27.6 27.6 27.4 27.2 27.0 26.7 26.3 25.9 25.5 25.0 24.5 24.0 23.5 23.0 22.6 22.1 21.5 21 .o 20.5 19.9 19.3 18.7 18.0 17.1 16.2 15.6 15.2 15.1

k (Wlm-K) 47.6 47.8

47.8 47.4 47.1 46.7 46.2 45.5 44.8 44.1 43.3 42.4 41.5 40.7 39.8 39.1 38.2 37.2 36.3 35.5 34.4 33.4 32.4 31.2 29.6 28.0 27.0 26.3 26.1

47.8

Temp ("C) 21 38 66 93 121 149 177 204 232 260 288 31 6 343 371 399 427 454 482 51 0

566 593 621 649 677 704 732 760 788 816

538

a (ft2/hr) 0.529 0.512 0.496 0.486 0.467 0.453 0.440 0.428 0.41 3 0.398 0.387 0.374 0.360 0.346 0.332 0.318 0.305 0.291 0.277 0.263 0.249 0.237 0.219 0.202 0.184 0.159 0.122 0.078 0.155 0.169

Cp (BtU/lb-"F) 0.106 0.1 10 0.113 0.116 0.119 0.122 0.125 0.127 0.130 0.133 0.134 0.136 0.139 0.141 0.144 0.147 0.151 0.155 0.158 0.163 0.168 0.171 0.1 79 0.189 0.199 0.219 0.270 0.407 0.200 0.182

Page 10 of 28

Cp (Jlkg-K) 443.3 459.6 474.0 484.2 500.3 512.0 523.2 531.9 543.0 554.9 561.8 570.0 580.3 591.4 603.5 616.7 631.8 647.6 661.8 680.8 702.0 71 5.9 751.4 789.3 834.1 91 7.0 1 132.2 1705.3 836.2 761.8

The emissivity of SA 5 16 is 0.80, which is the median of the values given in Reference 2 1, Table 4.3.2.

The density of SA 516 is 7850 kg/m3 (Ref. 1, SA 20/SA 20M, Section 14.1).

Table 5.1-5 provides the specific heat of the FSV Graphite Block. This was solved using the equations found on page 3 1 in Ref. 6.

The density of the FSV Graphite Block is given as 1740 kg/m3 in paragraph 2.1.2.4.14 on page 3 1 of Ref. 6.

The emissivity of the FSV Graphite Block is 0.75. This number was taken from the CRC Tables (Ref. 14, page 10-284) for graphite.

Waste Package Project Calculation Title: Thermal Evaluation of the Fort Saint Vrain Codisposal Waste Package Document Identifier: CAL-WIS-TH-000012 REV 00 Page 11 of 28

Table 5.1-5. Specific Heat of FSV Graphite Block

Temp ("C) 0

26.85 51.85 76.85 101.85 126.85 151.85 176.85 201.85 226.85 251.85 276.85 301.85 326.85 351.85 376.85 401.85 426.85 451.85 476.85 501.85 526.85 551.85 576.85 601.85 626.85 651.85 676.85 701.85 726.85 751.85 776.85 801.85 826.85 851.85 876.85 901.85 926.85 951.85 976.85 1001.85

Temp (K) 273.1 5 300 325 350 375 400 425 450 475 500 525 550 575 600 625 650 675 700 725 750 775 800 825 850 875 900 925 950 975 1000 1025 1050 1075 1100 1125 1150 1175 1200 1225 1250 1275

c p ( ca ' IgK)

0.15220261 7 0.170354406 0.187501214 0.204475151 0.220947593 0.236702145 0.25161 7734 0.265642178 0.278769243 0.291 021 585 0.302438883 0.313069897 0.32296731 0.332184461 0.340773353 0.348783499 0.35626131 1 0.363249842 0.36978874 1 0.375914347 0.381659859 0.387055539 0.3921 28944 0.396905149 0.401406968 0.405655163 0.409668637 0.413464617 0.41 7058808 0.42046555 0.423697944 0.426767977 0.429686625 0.432463954 0.4351 09206 0.437630875 0.440036778 0.4423341 19 0.444529542 0.446629185 0.448638724

c p (N-mlkgK)

637.3 713.3 785.1 856.1 925.1 991 .I 1053.5 1 1 12.2 1 167.2 1218.5 1266.3 131 0.8 1352.3 1390.9 1426.8 1460.4 1491.7 1520.9 1548.3 1574.0 1598.0 1620.6 1641.8 1661.8 1680.7 1698.5 1715.3 1731.2 1746.2 1760.5 1774.0 1786.9 1799.1 181 0.7 1821.8 1832.4 1842.4 1852.1 1861.2 1870.0 1878.5

Note: the conversion factor used in the right-most column is 4187 J/kg.K= 1 CB'/S-K

Table 5.1-6 provides the thermal conductivity of the FSV Graphite block. The values were found by solving the equations found on page 29 in Ref. 6.

Waste Package Pro-iect Calculation Title: Thermal Evaluation of the Fort Saint Vrain Codisposal Waste Package Document Identifier: CAL-WIS-TH-000012 REV 00 Page 12 of 28

Table 5.1-6. Thermal Conductivity of FSV Graphite Block

k, Unirradiated T ("C) (W/m-K)

23 27 77 127 177 227 277 327 377 427 477 527 577 627 677 727 777 827 877 927 977 1027 1077 1127 1177 1227 1277 1327 1377 1427 1477 1527

1 17.86 126.61 123.06 1 18.47 1 14.60 108.01 104.82 100.84 96.58 91.84 88.98 85.91 82.85 79.69 77.12 74.49 71.20 67.86 65.51 63.13 61.25 59.36 57.72 56.07 54.96 53.84 52.71 51 5 8 50.62 49.59 48.90 48.15

It should be noted that this is the thermal conductivity in the radial direction. Since this is a 2-D FEA representation, the radial direction is appropriate. The thermal conductivity listed here is for the unirradiated FSV block (Assumption 3.5).

The density and emissivity of Alloy 22 are as follows:

p = 8690 kg/m3 (Section 11, Part B, SB-575 of Ref. 1) Emissivity = 0.87 (Ref. 14, see Assumption 3.8)

Waste Package Proiect Calculation Title: Thermal Evaluation of the Fort Saint Vrain Codisposal Waste Package Document Identifier: CAL-WIS-TH-0000 12 REV 00 Page 13 of 28

Temperature ("C) 48 100 200 300 400 500 600

Table 5.1-7 provides the thermal conductivity and specific heat of Alloy 22. These values are from Ref. 1 5 , page 13.

Thermal Conductivity Specific Heat (Wlm-K) (Jlk,-K)

10.1 414 11.1 423 13.4 444 15.5 460 17.5 476 19.5 485 21.3 514

Table 5.1-7. Thermal Conductivity and Specific Heat of Alloy 22

The density of helium is known to be 0.1626 kg/m3 at 300 K (Ref. 7). thermal conductivity and specific heat of helium, found in Ref. 7 (Assumption 3 .3 ) .

Table 5.1-8 gives the

Table 5.1-8. Thermal Conductivity and Specific Heat of Helium

"C -17.78 -6.67 4.44 15.56 26.67 37.78 48.89 60.00 71 .I 1 82.22 93.33 1 1 5.56 137.78 160.00 182.22 204.44 226.67 248.89 271 .I 1 293.33 31 5.56 337.78 360.00

k (Wlm-K) 0.1396 0.1437 0.1478 0.1519 0.1559 0.1599 0.1638 0.1677 0.1715 0.1754 0.1791 0.1866 0.1940 0.2012 0.2083 0.2153 0.2222 0.2291 0.2358 0.2425 0.2491 0.2556 0.2684

Cp (Jlkg-K) 51 96 51 96 51 96 51 96 5196 51 96 5196 51 96 51 96 51 96 51 96 51 96 51 96 51 96 5196 51 96 51 96 51 96 5196 51 96 51 96 51 96 51 96

Waste Package Project Calculation

Document Identifier: CAL-WIS-TH-000012 REV 00 Page 14 of 28 I Title: Thermal Evaluation of the Fort Saint Vrain Codisposal Waste Package

The density of air is known to be 1,1774 kg/m3 at 300 K (Ref. 7). Table 5.1-9 gives the thermal conductivity and specific heat of air, found in Ref. 7, Chapter 19. Values marked with an asterisk were linearly interpolated from the table where values were missing.

Table 5.1-9. Thermal Conductivity and Specific Heat of Air

“C k (Wlm-K) -1 7.78 0.0229 -6.67 0.0237 4.44 0.0246 15.56 0.0254 26.67 0.0261 37.78 0.0269 48.89 0.0277 60.00 0.0284 71 .I 1 0.0292 82.22 0.0299 93.33 0.0307 11 5.56 0.0321

Cp (Jlkg-K) 1006 1006 1006 1006 1007 1007 1008 1008 1009 I010 101 1 1013

“C 137.78 160.00 182.22 204.44 226.67 248.89 271 .I 1 293.33 315.56 337.78 360.00

k (W/m-K) 0.0335 0.0349 0.0363 0.0377 0.0391 0.0405 0.0418 0.0432 0.0446 0.0459 0.0473

Cp (Jlkg-K) 1016 1019 1022 1026 1030 1035 1039 1044 1049 1054 1060

The properties pyrex will be used for borosillicate (Assumption 3.7), except for thermal conductivity. The properties are as follows:

Density: 2225 kg/m3 (Table A.3, Appendix A, Ref. 2) Thermal Conductivity: 1.1 W/m-K (Table 11.7, page 584, Ref. 20) Specific Heat: 835 J/kg-K (Table A.3, Appendix A, Ref. 2)

5.2 Finite Element Representation

To investigate the thermal response of the 5-DHLW/DOE SNF WP in the repository near field, a 2-D waste package cross-section representation is used to capture the temperature distribution inside the WP (Assumption 3.2). ANSYS Versions 5.6.2 and 5.4 finite element codes were used to create the 2-D thermal representation to calculate the temperatures.

A one-half symmetry of the WP cross-section was used to represent the whole WP in the ANSYS representation (Assumption 3.2). This is due to the one-fifth symmetry of the WP and the one-sixth symmetry of the FSV fuel block in the center of the WP. The five DHLW canisters are represented as “floating” in the DHLW WP baskets, such that there is no contact between the DHLW pour canisters and the WP basket. Further, each DHLW canister is positioned in the middle of the basket cell with gaps evenly distributed around the canister. The WP geometry may easily be viewed using the sketches in Attachment IV. The geometric dimensions of the Hanford Long canister were taken from Section 3.4 of Ref. 1 1.

The surface temperature of the WP was specified as a boundary condition. The temperatures were taken from Table 6-18 in Ref. 10 (Waste Package 1). Waste Package 1 was chosen because

Waste Package Proiect Calculation

Document Identifier: CAL-WIS-TH-0000 12 REV 00 Page 15 of 28 I Title: Thermal Evaluation of the Fort Saint Vrain Codisposal Waste Package

it has the closest heat generation as compared to the 5DHLW/DOE Long WP used in this calculation. However, Waste Package 1 does have more total Watts per canister than the 5DHLW/DOE Long with FSV fuel. Therefore, it is conservative to use Waste Package 1. The temperatures from Ref. 10 resulted from a calculation using an initial 50-year forced ventilation period and 0.1 meter spacing between WPs. The volumetric heat generation of the radioactive components was applied as body loads. The heat generation values were taken from Ref. 9 for the DHLW glass and from Ref. 6 for the FSV fuel.

The FSV fuel was represented as a homogeneous block with evenly distributed material (thermal) properties. In this way, the Finite Element Representation (FER) was simplified. However, a second FER was created with the details of the FSV hexagon included. The temperature of the FSV fuel from the first FER was applied to the second FER as a boundary condition. In effect, two separate FERs were created to do the job of one. However, two separate FERs could solve the mathematical representation more efficiently than one large FER.

Conduction and radiation were the only methods of heat transfer modeled. Convection within the WP was not considered (Assumption 3.4).

The ANSYS run was terminated at 1050 years after emplacement. The reason for ending the run at this time and not 10,000 years is because all temperatures peak within 100 years after emplacement. The calculation is allowed to solve until 1050 years after emplacement to obtain post peak temperature data.

5.3 Heat Load and Boundary Conditions

The heat generation is input into ANSYS as a volumetric heat generation rate. Therefore, the volume of the glass in the cylinder is needed.

The glass canister used for this calculation is the Hanford Long (Assumption 3.1). From Table RL-3 in Ref. 12, the canisters contain a glass volume of 1.08 m3 (Assumption 3.6). This allows the values from Ref. 9 to be divided by this number to obtain the volumetric heat generation of the DHLW glass.

The first FEA representation considers the fuel to be distributed equally throughout the entire hexagonal block. The length of the flat, s, for the FSV hexagon block is given as 8.182 in on page 14 of Reference 6. The area of such a hexagon is known to equal 2 .59808~~. Solving this equation using 8.182 inches for s yields an area of 173.929 in2, or 0.1 122 12 meter2. Since there are 5 fuel blocks in the WP and each fuel block is 3 1.22 inches long (page 14, Ref. 6), the total volume equals 271 50 in3, or 0.4448 m3.

The second FEA representation considers the volume of the fuel compacts only. There are 2 10 fuel compacts (Ref. 6, page 16), each having circular cross section ?4 inch in diameter. This gives 41.2334 in2, or 0.2660 m2. Multiplying by the total height of the five ( 5 ) FSV fuel blocks yields 6437 in3, or 0.1055 m3.

Table 5.3-1 lists the heat generation values of the DHLW glass on a volumetric basis.

Waste Package Pro-iect Calculation Title: Thermal Evaluation of the Fort Saint Vrain Codisposal Waste Package Document Identifier: CAL-WIS-TH-000012 REV 00 Page 16 of 28

Table 5.3-1. Heat Generation of DHLW Glass

Time (y) 0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44

~ / m ’ 52.21 51 .OO 49.80 48.60 47.48 46.37 45.26 44.15 43.13 42.1 1 41.10 40.17 39.24 38.32 37.39 36.56 35.63 34.80 34.06 33.22 32.39 31.65 30.91 30.17 29.52 28.78 28.13 27.48 26.83 26.18 25.63 24.98 24.42 23.87 23.31 22.76 22.20 21.64 21.18 20.72 20.16 19.70 19.24 18.87 18.40

Time (y) 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89

w/m3 17.94 17.57 17.1 1 16.74 16.36 15.99 15.62 15.25 14.88 14.51 14.23 13.86 13.58 13.21 12.94 12.66 12.29 12.01 11.73 11.45 11.27 10.99 10.71 10.43 10.25 9.97 9.78 9.51 9.32 9.1 1 8.89 8.69 8.49 8.29 8.1 1 7.92 7.74 7.56 7.39 7.23 7.06 6.89 6.73 6.59 6.44

Time (y) 90 91 92 93 94 95 96 97 98 99 100 110 120 130 140 150 160 170 180 190 200 250 300 350 400 450 500 550 600 650 700 750 800 850 900 950 1000 1500 2000 2500 3000 3500 4000 4500 5000

~ / m ’ 6.29 6.15 6.01 5.87 5.74 5.61 5.48 5.36 5.24 5.12 5.01 3.99 3.20 2.57 2.07 1.68 1.38 1.13 0.93 0.78 0.66 0.35 0.24 0.21 0.19 0.18 0.17 0.17 0.16 0.16 0.15 0.15 0.15 0.14 0.14 0.13 0.13 0.1 1 0.10 0.10 0.09 0.09 0.09 0.09 0.09

Time (y) 5500 6000 6500 7000 7500 8000 8500 9000 9500 10000 15000 20000 25000 30000 35000 40000 45000 50000 55000 60000 65000 70000 75000 80000 85000 90000 95000 100000 150000 200000 250000 300000 350000 400000 450000 500000 550000 600000 650000 700000 750000 800000 850000 900000 1000000

w/m3 0.09 0.08 0.08 0.08 0.08 0.08 0.08 0.08 0.08 0.08 0.07 0.06 0.05 0.05 0.04 0.04 0.03 0.03 0.03 0.03 0.02 0.02 0.02 0.02 0.02 0.02 0.02 0.02 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.01


The volumetric heat generation values for the FSV fuel were extrapolated from the values found in Reference 6. Attachment V details the extrapolation and resulting heat generation output of the FSV fuel. The values given in Table 5.3-2 are not on a volumetric basis. The values given in Table 5.3-2 are the total Watts produced per WP. They must be divided by the volume of the fuel before being used in ANSYS.

Table 5.3-2. Heat Generation of FSV Fuel

The surface temperature of the WP was taken from Table 6-18 in Ref. 10 under the heading “Waste Package 1”. “Waste Package 1” was chosen because it most closely matches 5DHLW/DOE with FSV fuel output in total heat generation (Watts). The temperatures used are listed in Table 5.3-3. It should be noted that this representation used an initial 50 year forced ventilation period with 0.‘1 meter spacing between waste packages. The sudden increase in temperature at 50 years is due to the end of the forced ventilation.


Table 5.3-3. WP Boundary Conditions

0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 2 3 4 5 6 7 8 9 10 15 20 25 30 35 40 45 50

50.01 50.02 50.03 50.04 50.05 50.06 50.07 50.08 50.09 50.1 50.2 50.3 50.4 50.5

36 56 62 65 67 69 71 72 74 75 76 83 86 88 90 91 92 92 92 93 92 91 89 87 85 83 82 80 87 95 100 103 105 107 108 110 110 111 116 119 121 124

50.6 50.7 50.8 50.9 51 52 53 54 55 56 57 58 59 60 70 80 90 100 110 120 130 140 150 250 350 450 550 650 750 850 950 1050 2050 3050 4050 5050 6050 7050 8050 9050 10050

128 129 130 131 141 148 152 155 158 161 162 163 163 163 163 159 155 152 150 147 144 141 128 123 119 116 113 110 109 107 106 93 87 83 80 77 75 73 71 69


6. RESULTS

This document may be affected by technical product input information that requires confirmation. Any changes to the document that may occur as a result of completing the confirmation activities will be reflected in subsequent revisions. The status of the technical product information quality may be confirmed by review of the DIRS database.

Figure 6-1 shows the mesh of the first FEA analysis. This picture shows the refinement of the mesh in critical areas and also displays the '/? symmetry of the representation.

I FSV Codisposal Waste P a c k a s e

Figure 6- 1 . FEA Mesh #1

Figure 6-2 may be found on the following page. It shows the peak temperatures in the cross section.


I ANSYS 5.4 JUN 11 2001 08 : 32: 58 P M T NO. 1 NODAL SOLUTION TIME=. 18 6E+10 TEHP SMN = I 6 3 SMX =I 73.68 5

166 .562

- 171.311 172.498 = 173.685

Figure 6-2. Maximum Temperatures from Mesh #1

Figure 6-2 shows the maximum temperatures in degrees Celsius resulting from Mesh #1. The time is approximately 59 years after emplacement.

Figure 6-3 may be found on the following page. It shows the temperature at the outer surface of the hexagonal block as a function of time.


173.560

168.831

158.192

A m 3 150.373 .rl

u

ar 142.(544

0

LL

I-

134.915

E 127.187

v

119.458

111.729

104.040

96.27 1

hext

I I I I I I C M IO**7>

0 554 I loa 1662 3216 2770 5524 277 83 1 1388 1939 2493 3047 3600

TIME ( s e c )

FSV C o d i s p o s a l Waste Package

Figure 6-3. Temperature vs. Time at outer surface of Hexagonal Block

Figure 6-3 temperatures are in Celsius. Time is in seconds. The values used for “hext” (node 9297) may be found in Attachment 11.

Figure 6-4 may be found on the following page. It shows the temperature versus time for three different locations in the DHLW glass. The location nearest the center of the WP is labeled “inner”. The location farthest from the center of the WP is labeled “outer”. The location labeled “middle” is in-between “inner” and “outer”.

Waste Package Project Calculation Title: Thermal Evaluation of the Fort Saint Vrain Codisposal Waste Package Document Identifier: CAL-WIS-TH-0000 12 REV 00 Page 22 of 28

AN. .

167.906

155.573

143,340

131.107

3 llb.874 1 Q

108.641

94.4-

82.176

69.943

57.710

4c1.478

inner

middle QUteK

FSV Codisposal Waste Package

Figure 6-4. Temperature vs. Time for DHLW glass

Figure 6-4 temperatures, labeled VALU, are in Celsius. Time is in seconds. The actual values for the variables “inner” (node 6772), “outer” (node 6832), and “middle” (node 6844) may be found in Attachment 11.

Figure 6-5 is found on the following page. It shows the mesh of the second FEA case, which solved only the FSV Fuel Block. The temperatures fiom the first FEA case (node “hext”) were applied as boundary conditions on the second FEA case. There was little or no difference in the temperature plots of the various nodes around the surface of the FSV fuel block fiom the first FEA case. Therefore, it is acceptable to use the temperature profile of only one node instead of the average of all or a selection of nodes.


AN

I FSV Fuel Block

Figure 6-5. FSV Fuel Block Mesh

Figure 6-5 shows the mesh of the second FEA case. This representation contained approximately 13,500 elements. This is actually more elements than the first FEA case. The representation was constructed from !A symmetry, which is why there is a strange concentration of nodes around the midline.

Figure 6-6 is found on the following page. It shows the temperature distribution in the FSV fuel block, which are the results from the second FEA case. Figure 6 is the time of highest temperature.

Waste Package Pro-iect Calculation Title: Thermal Evaluation of the Fort Saint Vrain Codisposal Waste Package Document Identifier: CAL-WIS-TH-000012 REV 00

FSV Fuel B lock

Page 24 of 28

ANSYS 5 . 6 . 2 J U N 25 2001 1 3 : 37 : 26 NODAL SOLUTION T I M E = . 186E+lO TEMP (AVG) RSYS=O PowerGraphic s E F A C E T = l AVRE S =Mat SMN =173.635 SMX =173.828

Figure 6-6. Max Temperatures in the FSV Fuel Block

The temperature range throughout the entire block is less than 1 degree. This is true at all points in time for the duration of the solution (1 000 years).

Figure 6-7 is a plot of temperature versus time for the hottest and coolest nodes in the hexagon. The nodes are the same at every point in time and are located as shown in Figure 6-5 by the labels “MX” and “MN”.

Waste Packape Proiect Calculation Title: Thermal Evaluation of the Fort Saint Vrain Codisposal Waste Package Document Identifier: CAL-WIS-TH-0000 12 REV 00 Page 25 of 28

173,732

166.004

1 sa. 2SB - v) 3 150.507

- 7 4

w

4) + 142.769

0 1 3 9 . 0 1 1

v

a x W 127.263 I-

119.515

111.767

loa. 019 nln

( x 10**n 96.271 0 554 1108 1662 2216 2770 3324

277 83 1 1385 1939 2493 3047 3600

TIME ( s e e 1

FSV Fuel B l o c k

Figure 6-7. Temp vs Time for the Bounding Nodes

Figure 6-7 demonstrates that the maximum and minimum temperatures in the FSV fuel block are nearly identical, varying by less than one degree at any instance. A possible explanation for this phenomenon is the excellent conductive properties of the graphite block. Attachment I11 lists the values used to create Figure 6-7. The node “max” is node 8905 and node “min” is node 7747.

Title: Thermal Evaluation of the Fort Saint Vrain Codisposal Waste Package Document Identifier: CAL-WIS-TH-0000 12 REV 00 Page 26 of 28

7. REFERENCES

1. ASME (American Society of Mechanical Engineers) 1998. 1998 ASME Boiler and Pressure Vessel Code. 1998 Edition with 1999 and 2000 Addenda. New York, New York: American Society of Mechanical Engineers. TIC: 247429.

2. Incropera, F.P. and DeWitt, D.P. Edition. New York, New York: John Wiley & Sons. TIC: 243950.

1996. Fundamentals of Heat and Mass Transfer. 4th

3. CRWMS M&O 2000. Software Code: ANSYS. V5.6.2. HP-UX 10.20. 10364-5.6.2-00.

4. CRWMS M&O 1997. Thermal Evaluations of the Codisposal Canister in the 5-Pack DHL W Waste Package. BBAA00000-0 17 17-0200-00021 REV 0 1. Las Vegas, Nevada: CRWMS M&O. ACC: MOL.19971210.0413.

5. Bird, R.B.; Stewart, W.E.; and Lightfoot, E.N. 1960. Transport Phenomena. New York, New York: John Wiley & Sons. TIC: 208957.

6. Taylor, L.L. 2001. Fort Saint Vrain HTGR (TWU Carbide) Fuel Characteristics for Disposal Criticality Analysis. DOE/SNF/REP-060, Rev. 0. [Washington, D.C.]: U.S. Department of Energy, Office of Environmental Management. TIC: 249783.

7. ASHRAE (American Society of Heating, Refrigerating & Air-conditioning Engineers) 1997. I997 ASHRAE Handbook, Fundamentals. Inch-Pound Edition. Atlanta, Georgia: American Society of Heating, Refrigerating and Air Conditioning Engineers. TIC: 240756.

8. ASTM G 1-90 (Reapproved 1999). 1990. Standard Practice for Preparing, Cleaning, and Evaluating Corrosion Test Specimens. West Conshohocken, Pennsylvania: American Society for Testing and Materials. TIC: 238771.

9. CRWMS M&O 2000. Source Terms for HLW Glass Canisters. CAL-MGR-NU-000002 REV 01. Las Vegas, Nevada: CRWMS M&O. ACC: MOL.200000823.0004.

10. CRWMS M&O 2000. Drift Scale Thermal Analysis. CAL-WIS-TH-000002 REV 00. Las Vegas, Nevada: CRWMS M&O. ACC: MOL.20000420.0401,

1 1. DOE (U.S. Department of Energy) 1992. Characteristics of Potential Repository Wastes. DOE/RW-O184-R1. Volume 1. Washington, D.C.: U.S. Department of Energy, Office of Civilian Radioactive Waste Management. ACC: HQO. 19920827.0001,

12. Picha, K.G., Jr. 1997. “Response to Repository Environmental Impact Statement Data Call for High-Level Waste.” Memorandum from K.G. Picha, Jr. (DOE) to W. Dixon (YMSCO), September 5, 1997, with attachments. ACC: MOL.19970917.0273.


13. CRWMS M&O 1995. Analysis of Degradation Due to Water and Gases in MPC. BB0000000-0 17 17-0200-00005 REV 0 1. Las Vegas, Nevada: CRWMS M&O. ACC: MOL. 19960419.0202.

14. Lide, D.R., ed. 1991. CRC Handbook of Chemistry and Physics. 72nd Edition. Boca Raton, Florida: CRC Press. TIC: 3595.

15. Haynes International 1997. Hastelloy C-22 Alloy. Kokomo, Indiana: Haynes International. TIC: 238121.

16. BSC (Bechtel SAIC Company) 2001. Technical Work Plan for: Waste Package Design Description for LA. TWP-EBS-MD-000004 REV 01. Las Vegas, Nevada: Bechtel SAIC Company. ACC: MOL.20010702.0152.

17. AP-3.12Q, Rev. 0, ICN 4. Calculations. Washington, D.C.: U.S. Department of Energy, Office of Civilian Radioactive Waste Management. ACC: MOL.20010404.0008.

18. AP-SI.lQ, Rev. 3, ICN 1, ECN 1. Software Management. Washington, D.C.: U.S. Department of Energy, Office of Civilian Radioactive Waste Management. ACC: MOL.20010705.0239.

19. AP-SV.lQ, Rev. 0, ICN 2. Control of the Electronic Management of Information. Washington, D.C.: U.S. Department of Energy, Office of Civilian Radioactive Waste Management. ACC: MOL. 2000083 1.0065.

20. Benedict, M.; Pigford, T.H.; and Levi, H.W. 1981. Nuclear Chemical Engineering. 2nd Edition. New York, New York: McGraw-Hill. TIC: 245089.

21. Avallone, E.A. and Baumeister, T., 111, eds. 1987. Marks’ Standard Handbook for Mechanical Engineers. 9th Edition. New York, New York: McGraw-Hill. TIC: 206891.

22. CRWMS M&O 1998. ANSYS. V5.4. HP-UX 10.20. 30040 5.4.

23. DOE (U.S. Department of Energy) 1998. Design Specification. Volume 1 of Preliminary Design Spec2fcation for Department of Energy Standardized Spent Nuclear Fuel Canisters. DOE/SNF/REP-01 1, Rev. 1. Washington , D.C.: U.S. Department of Energy, Office of Spent Fuel Management and Special Projects. TIC: 241528.

24. DOE (U.S. Department of Energy) 1999. Waste Acceptance System Requirements Document. DOE/RW-0351, Rev. 03. Washington, D.C.: U.S. Department of Energy, Office of Civilian Radioactive Waste Management. ACC: HQO. 19990226.0001.

25. Parrington, J.R.; Knox, H.D.; Breneman, S.L.; Baum, E.M.; and Feiner, F. 1996. Nuclides and Isotopes, Chart of the Nuclides. 15th Edition. San Jose, California: General Electric Company and KAPL, Inc. TIC: 233705.


Description fine.out fsv.dat

fsvfuel.dat hext.parm

26. CRWMS M&O 2000. Defense High Level Waste Disposal Container System Description Document. SDD-DDC-SE-000001 REV 01. Las Vegas, Nevada: CRWMS M&O. ACC: MOL.20000823.0001

Date Time Si% ~

06/25/2001 4:23 PM 3,069 KB 06/25/2001 4:24 PM 17 KB 06/25/2001 4:24 PM 2 KB 06/25/2001 4:23 PM 8 KB

27. ASM International 1987. Corrosion. Volume 13 of ASM Handbook. 9th Edition. Materials Park, Ohio: ASM International. TIC: 240704.

Description fine.out fsv.dat

fsvfuel.dat hext.parm

8. ATTACHMENTS

Date Time Si% ~

06/25/2001 4:23 PM 3,069 KB 06/25/2001 4:24 PM 17 KB 06/25/2001 4:24 PM 2 KB 06/25/2001 4:23 PM 8 KB

Attachment I (compact disc):

Attachment I1 (2 pages):

Attachment I11 (2 pages):

Attachment IV (3 pages):

Attachment V (3 pages):

contains electronic files (see Table 8-1 for a complete list). The folders FEAl and FEA2 are the two FEA cases as explained in Section 5.2. The input files are echoed back at the beginning of the *.out files. The input files call all the other files except for the *.out files. These are the material property, boundary condition, and heat generation files.

Table of values used to create Figure 3 and Figure 4.

Table of values used to create Figure 7.

Design sketches (5 DHLW/DOE SNF - Long Waste Package Configuration for Site Recommendation [SK-0200 REV 041, and 5 DHLW/DOE - Long Weld Configuration [SK-0201 REV 001).

Spreadsheet and explanation for the total heat generation (in Watts) for the 5 DHLW/DOE Long WP with FSV fuel.

Table 8-1 provides a list of attachments submitted in the form of electronic files (compact disc) in Attachment I.

Table 8-1. List of Attachments Submitted in the Form of Electronic Files in Attachment I

Description Time Size fsv.dat 06/25/2001 4:24 PM

fsvfuel.dat 06/25/2001 4:24 PM 06/25/2001 4:24 PM

jg.out 06/25/2001 4:24 PM 1,064 KB

FEA2

NOTE: The file sizes may vary with operating system.

CAL-WIS-TH-0000 12 REV 00 Attachment I1 Page 11- 1

STORAGE COMPLETE FOR 71 DATA POINTS

SUMMARY OF VARIABLES STORED THIS STEP AND EXTREME VALUES VARI TYPE IDENTIFIERS NAME MINIMUM AT TIME MAXIMUM AT TIME

2 NSOL 6772 TEMP inner 57.63 31.56 167.4 3 NSOL 6844 TEMP middle 51.93 0.1000E-05 165.8 4 NSOL 6832 TEMP outer 46.68 0.1000E-05 164.4 5 NSOL 9297 TEMP hext 96.27 0.1000E-05 173.6

***** ANSYS POST26 VARIABLE LISTING *****

0.18623+10 0.18623+10 0.18623+10 0.18623+10

TIME

0.10000E-05 31.558 0.315583+07 0.631163+07 0.946733+07 0.126233+08 0.157793+08 0.189353+08 0.220903+08 0.252463+08 0.284023+08 0.315583+08 0.631153+08 0.946733+08 0.126233+09 0.157793+09 0.189353+09 0.22090E+09 0.252463+09 0.284023+09

6772 TEMP inner 57.6322 57.6322 75.4290 81.5642 84.7697 87.0963 88.9763 90.5643 91.9158 93.1143 94.1753 95.1149 101.095 104.090 105.814 106.912 107.543 107.856 107.993 107.950

6844 TEMP middle 51.9315 51.9315 69.7374 75.8387 79.0461 81.3794 83.2678 84.8652 86.2264 87.4350 88.5062 89.4561 95.5452 98.6522 100.490 101.702 102.449 102.877 103.131 103.204

6832 TEMP outer 46.6774 46.6774 64.8088 70.5944 73.7589 76.0786 77.9630 79.5607 80.9240 82.1372 83.2137 84.1697 90.3489 93.5554 95.4975 96.8168 97.6716 98.2096 98.5706 98.7520

9297 TEMP hext 96.2713 96.2713 110.281 115.290 117.865 119.722 121.215 122.471 123.533 124.471 125.296 126.022 130.468 132.444 133.356 133.742 133.732 133.450 133.014 132.422


TIME

0.315583+09 0.631153+09 0.946733+09 0.126233+10 0.157793+10 0.157823+10 0.157853+10 0.15788E+10 0.157913+10 0.157953+10 0.157983+10 0.15801E+10 0.158043+10 0.158073+10 0.15810E+10

6772 TEMP inner 107.722 102.993 96.9321 91.3032 86.4573 89.6590 96.0932 102.283 106.617 109.449 111.635 113.181 114.785 115.706 116.409

6844 TEMP middle 103.094 99.2853 93.9578 88.9092 84.5251 87.8513 94.3813 100.547 104.819 107.606 109.775 111.297 112.912 113 - 798 114.504

6832 TEMP outer 98.7494 95.8248 91.1961 86.7048 82.7577 87.1646 94.2141 100.036 103.872 106.373 108.466 109.806 111.535 112.125 112.913

9297 TEMP hext 131.666 122.960 113.718 105.400 98.2633 100.911 106.722 112.607 116.818 119.578 121.666 123.176 124.659 125.608 126.256

CAL-WIS-TH-000012 REV 00 Attachment I1 Page 11-2

0.158423+10 121.573 119.664 117.998 0.158733+10 124.654 122.741 121.033 0.159053+10 126.681 124.769 123.042 0.159373+10 129.567 127.664 125.963 0.159683+10 131.594 129.691 127.972


TIME

0.16000E+10 0.16031E+10 0.160633+10 0.160943+10 0.16410E+10 0.167263+10 0.17041E+10 0.173573+10 0.176723+10 0.179883+10 0.183033+10 0.186193+10 0.189353+10 0.220903+10 0.252463+10 0.284023+10 0.31558E+10 0.347133+10 0.378693+10 0.410253+10

6772 TEMP inner 133.558 134.597 135.573 136.549 146.316 153.144 157.009 159.880 162.742 165.610 166.507 167.397 167.303 166.479 165.826 161.327 157.114 153.906 151.706 148.517

6844 TEMP middle 131.659 132.699 133.679 134.659 144.468 151.336 155.239 158.149 161.049 163.957 164.889 165.817 165.759 165.222 164.800 160.483 156.331 153.188 151.053 147.932

6832 TEMP outer 129.943 130.964 131.948 132.932 142.779 149.678 153.612 156.554 159.492 162.434 163.398 164.359 164.332 164.073 163.869 159.724 155.656 152.589 150.524 147.467

131.140 134.052 135.962 138.676 140.590

9297 TEMP hext 142.439 143.417 144.329 145.242 154.399 160.783 164.344 166.958 169.568 172.191 172.916 173.635 173.403 171.473 169.926 164.777 160.364 156.929 154.475 151.039


TIME

0.441813+10 0.473363+10 0.788943+10 0.11045E+ll 0.14201E+ll 0.173573+11 0.205123+11 0.236683+11 0.268243+11 0.299803+11 0.33135E+11

6772 TEMP inner 145.334 142.154 128.274 123.126 119.081 116.062 113.052 110.046 109.042 107.039 106.038

6844 TEMP middle 144.816 141.705 128.169 123.080 119.053 116.042 113.036 110.032 109.029 107.028 106.027

6832 TEMP outer 144.412 141.359 128.089 123.043 119.029 116.023 113.020 110.018 109.017 107.016 106.015

9297 TEMP hext 147.596 144.147 128.779 123.355 119.224 116.167 113.138 110.122 109.111 107.105 106.101

CAL-WIS-TH-000012 REV 00 Attachment I11 Page 111- I


TIME

0.10000E-05 31.558 0.315583+07 0.631163+07 0.946733+07 0.126233+08 0.157793+08 0.189353+08 0.22090E+08 0.252463+08 0.284023+08 0.315583+08 0.631153+08 0.946733+08 0.126233+09 0.157793+09 0.189353+09 0.220903+09 0.252463+09 0.284023+09

8905 TEMP max 96.9391 96.9391 110.953 115.963 118.538 120.394 121.886 123.142 124.203 125.140 125.964 126.689 131.124 133.086 133.985 134 -357 134.334 134.038 133.588 132.982

7747 TEMP min 96.2713 96.2713 110.281 115.290 117.865 119.722 121.215 122.471 123.533 124.471 125.296 126.022 130.468 132.444 133.356 133.742 133.732 133.450 133.014 132.422


TIME

0.315583+09 0.631153+09 0.946733+09 0.126233+10 0.15779E+10 0.157823+10 0.157853+10 0.157883+10 0.157913+10 0.157953+10 0.157983+10 0.15801E+10 0.15804E+10 0.158073+10 0.15810E+10 0.158423+10 0.158733+10 0.159053+10 0.159373+10 0.159683+10

8905 TEMP max 132.212 123.394 114.064 105.677 98.4862 101.092 107.161 113.204 117.333 119.512 121.705 123.347 124.898 125.878 126.535 131.352 134.305 136.189 138.868 140.825

7747 TEMP min 131.666 122.960 113.718 105.400 98.2638 100.872 106.941 112.983 117.110 119.288 121.481 123.121 124.674 125.652 126.311 131.127 134.080 135.965 138.641 140.598


TIME 8905 TEMP 7747 TEMP

CAL-WIS-TH-000012 REV 00 Attachment 111

0.16000E+10 0.16031E+10 0.160633+10 0.160943+10 0.16410E+10 0.167263+10 0.17041E+10 0.173573+10 0.176723+10 0.179883+10 0.183033+10 0.186193+10 0.189353+10 0.220903+10 0.252463+10 0.284023+10 0.315583+10 0.347133+10 0.378693+10 0.410253+10

max 142.648 143.649 144.550 145.477 154.620 160.992 164.559 167.166 169.776 172.392 173.114 173.828 173.592 171.626 170.050 164.879 160.458 157.014 154.551 151.107

min 142.422 143.424 144.324 145.253 154.398 160.773 164.345 166.955 169.570 172.190 172.917 173.635 173.403 171.473 169.926 164.777 160.365 156.929 154.475 151.039


TIME

0.441813+10 0.473363+10 0.788943+10 0.11045E+ll 0.14201E+ll 0.173573+11 0.205123+11 0.236683+11 0.268243+11 0.299803+11 0.331353+11

8905 TEMP max 147.656 144.199 128.791 123 -360 119.227 116.170 113.139 110.124 109.112 107.107 106.102

7747 TEMP min 147.596 144.147 128.779 123.355 119.224 116.167 113.138 110.122 109.111 107.105 106.101

Page 111-2

5; 7

4 I NNEl

COLLAR

SHELL

SLEEVE OD

L I D L IFT ING FEATURE OD

$6 1983. OUTER SHELL CLOSURE L I D

$61997 OUTER SHELL EXTENDED L I D

S

\

+-,@I886 INNER SHELL L I D 4

@ I 9 8 6 OUTER SHELL L I D

SECTION A-A 'I SEE DETAIL B

SHEET 2

2 9

I .ENGTH

,- fl501.5 SUPPORT $63860 INNER SHELL I D 7

@ I 9 8 0 INNER SHELL OD

@ 1980 OUTER SHELL I D $62030 OUTER SHELL OD

9 0

18' CANISTER LONG I WP ASSEMBLY WITH SNF I 56331 I - I

I \\

-1Ij13.5 T Y P 4

TUBE I D

TUBE OD

REVISONS ORWBY DATE E v mQ3mKIN

00 ISSUED APPROVED DGM 1/25/00 01 INNER SHELL L I D THiCKNESS 105 'WAS' 80 IN TABLE , DGM 1 / 2 6 / 0 0

DGM 2 / 9 / 0 0 02 OUTER SHELL THltKNESS 25 'WAS' 20 I N TABLE

o3 SKETCHED e y 'WAS. ORIGINATOR, VIEDESIGNED- REVISION BLOCK, EJC 3 1 2 / o o SDHLW-LONG 'WAS' NEW-LONG, 'ADDED' VIEW '0' TO SHEET 2 I N NOTE * a , DOEIRW-0351 'WAS' DOEIRW-3ISP EJC 6 / 5 / 0 0 0 4

"FOR INFORMATION ONLY' I

I * UNITED STLTES DEPARTMENT OF ENERGY 1998. DESIGN SPECIFICATION FOR DEPARTMENT OF ENERGY STANDARDIZED SPENT NUCLEAR FUEL CANISTERS. VOLUME I. DESIGN SPZCIFICATION, REV 01 WASHINGTON D.C.: UNITED STATES DEPARTMENT OF ENERGY. TIC: 241528

5 c ) # W / w E SNF - LONG WASTE PACKAGE COWIGURATION FOR SITE RECOMMENDATION -

@ @ @ WASTE ACCEPTANCE SYSTEM REOUIREMENTS DOCUMENT. E00000000-00811-1708-00001 REV 0 3 , SKETCH NUWOt SK-0200 REV 04 SHEET I OF 2 DOEIRW-0351. ACC: HQO. 19990226.0001. PAGE 18, SECTION 4.2.3. I .A .4 . @ By: EUGENE CONNELL c(pc f/'/o 5% srrL %g!!

06/05/00 @ e * SEE SK-0201 FOR WELD CONFIGURATION AND MASSES

69 UNITS: mm DO NOT SCALE FROM SKETCH FLE: I b m t l p r e ~ l i b r o r ~ l t h e t k a m t i k ~ e i c b e ~ l S d ~ l ~ l ~ d b l ~ . l ~ ~ a i ~ k - O l ~ 2 r e ~ O 4 . d w

I I 25 T I P

TypT r 1 EXTENDED OUTER SHELL L I D

3

R3 I NDED L I D REINFORCEMENT

25 EXTENDED L I D BASE

30 CLOSURE L I D TO EXTENDED OUTER L I D

>d 90mx /d I I O CLOSURE L I D WELD

r T I P 2 PL 10 CLOSURE L I D

30 INNER SHELL L I D TO CLOSURE L I D GAP

I D

- 5 . 7 T I P 2 PL

3 T I P 2 PL

GAP

'T G!3 DETAIL D

DETAIL B

+@205 TYP-4

OUTER L I D L l f T l N G FEATURE

21 T I P IS T I P

INNER L I D L l f T l N G FEATURE

F L A l

40

c-

i I 'F- 20 l-

0 0

5 c\1

0 0 0

M

DETAIL A DETAIL C

7 6 5 4 8

r 0 Z l l O TRUNNlON COLLAR SLEEVE OD

7 S E I DETAIL A

SEE DETAIL 8 S E C T I O N A - A S C A L E 0 . 0 6 2

5 D E T A I L A S C A L E 0 . 6 0 9 7

\-+ T D D E T A I L B S C A L E 0 . 6 0 9

S T l U C l U l A l LEAD

U I U r K I U 1 1 1 6 WE JERRY COGAR

SCOTT BENNETT . 5 DHLlllVVL UICI n r n r i i

w'nnr S N F - LONG DIMENSIONS ARE I N MILLIMETERS tDLsi6t GKW WR I s A W L L U LWIIF I G U R A T ION

K V l KIM -- _. ... AND DEGRIES UNLESS 0 SKCTCH I U I C I

W NOT SCALE FII, I vv SI- 020 I

JCMC . 0 6 Z I ISHLET I OF I ~

2 I

CAL-WIS-TH-000012 REV00 Attachment V Page V1 Of4

Decay Heat Calculation for Ft. St. Vrain HTGR fuel

The maximum decay heat generated by the Ft. St. Vrain HTGR spent nuclear fuel at various times is calculated in the Excel spreadsheet “FSV-thermal-source-term.xls”, using the method presented below.

The thermal output power generated by the nuclide “j” is proportional to the nuclide’s activity at any given time:

where:

Hj(ti) is the heat ouput (in W) from nuclide ‘7” at time ti. Aj(ti) is the activity (in Ci) of nuclide ‘7’’ at time ti. Kj is a constant (in W/Ci) that is specific to each nuclide ‘7’’ (taken from Ref. 11).

For nuclides that do not have a “parent” nuclide from which they are forming (or there are no “parent” nuclides left as a result of disintegration), the following equation is used for calculating the activity at the desired time ti:

Ref. 20, Chapter 2

where:

Aj(ti) is the activity of nuclide “j” at time ti. Aj(t0) is the activity of nuclide “f’ at reference time to (year 2010) (taken fiom Ref. 6). TJ1/2 is the half life of nuclide “j” (taken from Ref. 25).

For the nuclides subject to “ingrowth” from their parents decay (i.e., nuclide “B” in a chain like A+B+C) the following equation is used for calculating the activity at the desired time ti:

Ref. 20, Chapter 2

where:

AA(ti) is the activity of nuclide A (parent) at time ti. AA(tO) is the activity of nuclide A (parent) at reference time to (year 2010) (taken from

TA1/2 is the half life of nuclide A (taken from Ref. 25). Ae(ti) is the activity of nuclide B (daughter) at time ti.

Ref. 6) .

CAL-WIS-TH-0000 12 REV00 Attachment V Page V2 of4

fiA(fO) is the activity of nuclide B (daughter) at reference time to (year 2010) (taken from

TA1,2 is the half life of nuclide A (taken from Ref. 25). Ref. 6).

CAL-WIS-TH-000012 REV 00 Attachment V Page V3 of 4

Fort Saint Vrain HTGR Spent Nudtar t

Isotope Half-life Thermal powel

(years)' C-14 5.730E+03 CI-36 3.010E+05

Ni-63 1.000E+02 Se79 6.500E+05

Y-90 7.312E-03

Ni-59 7.600E+04

Sr-90 2.878E+01

Zr-93 1.500E+06 Nb-93M 1.610E+01 To99 2.130E+05 Pd-107 6.500E+06 Sn-126 2.500E+05 1-129 1.570E+07 Cs-135 2.300E+06

Ba-137m 4.850E-06 Sm-151 9.000E+01 Pb-210* 2.260E+01 Ra-226' 1.599E+03 Ra-228' 5.760E+00

CS-137 3.007E+01

Th-229' 7.300E+03 Th-230' 7.540E+04 Th-232 1.400E+10

U-233 1.592E+05 U-234 2.460E+05 U-235' 7.040E+08 U-236' 2.342E+07 U-238 4.470E+09 Np237' 2.140E+06 Pu-238 8.770E+01 Pu-239 2.410E+04 Pu-240' 6.560E+03 Am-241 4.327E+02 Am242M 1.410E+02 Am-243 7.370E+03 Cm244 1.810E+Ol Cm245 8.500E+03

Pa-231' 3.280E+04

(WICi) 2.933E-04 1.475E-03 3.972E-05 1.008E-04 2.490E-04 1.161 E-03 5.543 E-03 1.162E-04 1.772E-04 5.01 5E-04 5.928E-05 1.247E-03 4.626E-04 3.338E-04 1.106E-03 3.927E-03 1.173E-04 2.317E-04 2.888E-02 7.707E-05 3.059E-02 2.830E-02 2.421E-02 3.013E-02 2.907E-03 2.88OE-02 2.619E-02 2.709E-02 2.537E-02 3.057E-02 3.31 4E-02 3.082E-02 3.114E-02 3.322E-02 3.950E-04 3.215E-02 3.498E-02 3.319E-02

Cm-246 4.760E+03 3.274E-02 l~ota i (WIDOE SNF canister)

?I Maximum Th Year 2010

Ci/MTHM (avg.: 6.5251E+01 7.6985E-01 5.3712E+00 1.3582E+02 8.3082E+00 9.422€+05 9.422E+05 3.3713E+02 3.2852E-06 2.1052E+02 2.4423E-01 3.3906E+00 6.0366E-01 3.9595E+00 9.9405E+05 9.9405E+05 1.5653E+04 8.1456E-04 8.5551E-04 1.9336E+00 4.6581E+00 3.5645E-01 1.5451 E+OO 5.6473E+00 2.0507E+03 1.6099E+02 5.8667E-01 5.8632E+00 1.5267E-02 4.31 81 E+OO 2.2915E+04 5.9855E+01 1.0636E+02 1.0144E+03 1.3635E-01 7.3985E+00 3.3817E+02 6.6947E-02 1.9203E-02

mal Power Year Year Year Year Year Year Year Year Year Year Year Year 2010 2020 2030 2040 2050 2060 2070 2080 2090 2100 2200 2300

(WMTHM) (WMTHM) (WMTHM) (WMTHM) (WMTHM) (WMTHM) (WMTHM) (WMTHM) (WMTHM) (WMTHM) (WMTHM) (WMTHM) 1.9138E-02 1.9115E-02 1.9092E-02 1.9069E-02 1.9046E-02 1.9023E-02 1.9000E-02 1.8977E-02 1.8954E-02 1.8931E-02 1.8703E-02 1.8478E-02 1.1355E-03 1.1 355E-03 1.1355E-03 1.1355E-03 1.1 354E-03 1.1354E-03 1.1354E-03 1.1353E-03 1.1353E-03 1.1353E-03 1.1 350E-03 1.1348E-03 2.1334E-04 2.1332E-04 2.1331E-04 2.1329E-04 2.1327E-04 2.1325E-04 2.1323E-04 2.1321E-04 2.1319E-04 2.1317E-04 2.1297E-04 2.1278E-04 1.3691 E-02 1.2774E-02 1.1918E-02 1.1 120E-02 1.0376E-02 9.6808E-03 9.0325E-03 8.4276E-03 7.8632E-03 7.3366E-03 3.6683E-03 1.8342E-03 2.0687E-03 2.0687E-03 2.0687E-03 2.0687E-03 2.0687E-03 2.0686E-03 2.0686E-03 2.0686E-03 2.0686E-03 2.0685E-03 2.0683E-03 2.0681E-03 1.0939E+03 8.5976E+02 6.7574E+02 5.31 11E+02 4.1743E+02 3.2809E+02 2.5787€+02 2.0X7E+02 1.5929E+02 1.2520E+02 1.1262E+01 1.0131E+00 5.2226E+0314.1058E+0313.2270E+03j 2.5363E+03 I 1.9935E+03~1.5668E+03~1.2314E+03~ 9.6788E+02 ]7.6072E+0215.9790E+0215.3784E+Ol I 4.8382E+OO] 3.9175E-02 3.9174E-02 3.9174E-02 3.9174E-02 3.9174E-02 3.9174E-02 3.9173E-02 3.9173E-02 3.9173E-02 3.9173E-02 3.9171E-02 3.9169E-02 5.8214E-10 I 2.0899E-02 I 3.4486E-02 I 4.3320E-02 I 4.9064E-02 I 5.2798E-02 I 5.5226E-02 I 5.6804E-02 I 5.7830E-02 I 5.8497E-02 I 5.9718E-02 I 5.9732E-021 1.0558E-01 1.0557E-01 1.0557E-01 1.0557E-01 1.0556E-01 1.0556E-01 1.0556E-01 1.0555E-01 1.0555E-01 1.0554E-01 1.0551E-01 1.0548E-01 1.4478E-05 1.4478E-05 1.4478E-05 1.4478E-05 1.4478E-05 1.4478E-05 1.4478E-05 1.4478E-05 1.4478E-05 1.4478E-05 1.4478E-05 1.4478E-05 4.2281 E-03 4.2280E-03 4.2278E-03 4.2277E-03 4.2276E-03 4.2275E-03 4.2274E-03 4.2273E-03 4.2271 E-03 4.227OE-03 4.2259E-03 4.2247E-03 2.7925E-04 2.7925E-04 2.7925E-04 2.7925E-04 2.7925E-04 2.7925E-04 2.7925E-04 2.7925E-04 2.7925E-04 2.7925E-04 2.7925E-04 2.7925E-04 1.3217E-03 1.3217E-03 1.3217E-03 1.3217E-03 1.3217E-03 1.3217E-03 1.3217E-03 1.3217E-03 1.3216E-03 1.3216E-03 1.3216E-03 1.3216E-03

1.8447E+00 1.8442E+00 1.8437E+00 1.8431E+00 1.8426E+00 1.8421E+00 1.8416E+00 1.8410E+00 1.8405E+00 1.8400E+00 1.8347E+00 1.8294EWO

3.3698E+01 3.3163E+Ol 3.2636E+01 3.2117E+01 3.1607E+01 3.1 105E+01 3.0610E+01 3.0124E+01 2.9645E+01 2.9174E+01 2.4856E+Ol 2.1 177E+Ol' 5.3858E-05 5.1275E-05 4.8815E-05 4.6473E-05 4.4244E-05 4.2122E-05 4.0101E-05 3.8177E-05 3.6346E-05 3.4602E-05 2.1 165E-05 1.2945E-05 2.3786E-01 2.3764E-01 2.3741E-01 2.3719E-01 2.3697E-01 2.3675E-01 2.3652E-01 2.36306-01 2.3608E-01 2.3586E-01 2.3365E-01 2.3146E-01 1.1829E+01 8.0657E+OO 5.4995E+00 3.7498€+00 2.5568E+00 1.7433E+00 1.1887E+00 8.1050E-01 5.5263E-01 3.7681E-01 8.184lE-03 1.7776E-04 2.2220E-03 2.2202E-03 2.2183E-03 2.2165E-03 2.2147E-03 2.2129E-03 2.211 lE-03 2.2093E-03 2.2075E-03 2.2057E-03 2.1878E-03 2.1700E-03 6.2871E-04 6.2779E-04 6.2688E-04 6.2597E-04 6.2505E-04 6.2415E-04 6.2324E-04 6.2233E-04 6.2142E-04 6 2052E-04 6 1155E-04 6 0771FnA

3.3121E+00~3.3105E+00) 3.3090E+00] 3.3075E+00 I 3.3059E+00~3.3044E+00~3.3029E+00~ 3.3014E+00 ~3.2998E+00~3.2983E+00~3.2832E+00~3.2681E~O

* Isotopes subject to 'ingtuwth' because of 'parent' decay; 'calculated' concentations (2030 and beyond) from year 2010 values ** Maximum MTHM per standard canister: (0.012785 MTHMESV FUEL ELEMENT) x (5 FSV FUEL ELEMENTWOE SNF CANISTER) = 0.063925 MTmWDOE SNF CANISTER

a. Half-lives from Ref. 25. b. Template values Table Dl. Ref. 6

CAL-WS-TH-000012 REV 00 Attachment V Page V4 of 4

Year Year Year Year Year Year Year Year Year Year Year Year Year Year Year Year 2400 2500 2600 no0 2800 2900 3000 4000 5000 6000 7000 8000 9000 lo000 11000 12000

(WMTHM) (WIMTHM) (WIMTHM) (WIMTHM) (WIMTHM) (WIMTHM) (WIMTHM) (WIMTHM) (WIMTHM) (WIMTHM) (WIMTHM) (WIMTHM) (WIMTHM) (WIMTHM) (WMTHM) (WIMTHM) 1.8256E-02 1.8037E-02 1.7820E-02 1.7606E-02 1.7394E-02 1.7185E-02 1.6978E-02 1.5044E-02 1.3330E-02 1.181 1E-02 1.0465E-02 9.2728E-03 8.2163E-03 7.2801E-03 6.4506E-03 5.7157E-03 1.1 345E-03 1.1 342E-03 1.1340E-03 1.1 337E-03 1.1335E-03 1.1332E-03 1.1329E-03 1.1303E-03 1.1277E-03 1,1251E-03 1.1226E-03 1.1200E-03 1 .1174E-03 1.1 148E-03 1.1 123E-03 1 .1097E-03 2.1259E-04 2.1239E-04 2.1220E-04 2.1201E-04 2.1181E-04 2.1162E-04 2.1 143E-04 2.0951E-04 2.0760E-04 2.0572E-04 2.0385E-04 2.0200E-04 2.0017E-04 1.9835E-04 1.9655E-04 1.9477E-04 9.1708E-04 4.5854E-04 2.2927E-04 1.1464E-04 5.7318E-05 2.8659E-05 1.4329E-05 1.3994E-08 1.3666E-11 1.3345E-14 1.3032E-17 1.2727E-20 1.2429E-23 1.2137E-26 1.1853E-29 1.1575E-32 2.0679E-03 2.0677E-03 2.0674E-03 2.0672E-03 2.0670E-03 2.0668E-03 2.0666E-03 2.0644E-03 2.0622E-03 2.0600E-03 2.0578E-03 2.0556E-03 2.0524E-03 2.0512E-03 2.0490E-03 2.0468E-03 9.1 WE-02 8.1983E-03 7.3749E-04 6.6342E-05 5.9678E-06 5.36-E-07 4.8292E-08 1.6757E-18 5.8142E-29 2.0174E-39 7.0001 E-50 2.4289E-60 8.4278E-71 2.9243E-81 1.0147E-91 3.5207E-102

3.9167E-02 3.9166E-02 3.9164E-02 3.9162E-02 3.9160E-02 3.9158E-02 3.9157E-02 3.9138E-02 3.9120E-02 3.9102E-02 3.90-E-02 3.9066E-02 3.9048E-02 3.9030E-02 3.9012E-02 3.8994E-02

1.0544E-01 1.0541E-01 1.0537E-01 1.0534E-01 1.0530E-01 1.0527E-01 1.0524E-01 1.0489E-01 1.0455E-01 1.0421E-01 1.0388E-01 1.0354E-01 1.0320E-01 1.0287E-01 1.0253E-01 1.0220E-01 1.4477E-05 1.4477E-05 1.4477E-05 1.4477E-05 1.4477E-05 1.4477E-05 1.4476E-05 1.4475E-05 1.4473E-05 1.4472E-05 1.4470E-05 1.4469E-05 1.4467E-05 1.4466E-05 1.4464E-05 1.4463E-05 4.223%-03 4.2223E-03 4.2212E-03 4.2200E-03 4.2188E-03 4.2177E-03 4.2165E-03 4.2048E-03 4.1932E-03 4.1816E-03 4.1700E-03 4.1584E-03 4.1469E-03 4.1354E-03 4.1240E-03 4.1 126E-03 2.7925E-04 2.7925E-04 2.7925E-04 2.7924E-04 2.7924E-04 2.7924E-04 2.7924E-04 2.7923E-04 2.7922E-04 2.792OE-04 2.7919E-04 2.7918E-04 2.7917E-04 2.7915E-04 2.7914E-04 2.7913E-04 1.3215E-03 1.3215E-03 1.3214E-03 1.3214E-03 1.3214E-03 1.3213E-03 1.3213E-03 1.3209E-03 1.3205E-03 1.3201E-03 1.3197E-03 1.3193E-03 1.3189E-03 1.3185E-03 1.3181E-03 1.3177E-03

14.3523E-01 I 3.9151E-02 I 3.5219E-03 I 3.1682E-04 I 2.8500E-05 I 2.5637E-06 I 2.3062E-07 I 8.0022E-18 I 2.7766E-28 I 9.6343E-39 I 3.3429E-49 I 1.1599E-59 I 4.0247E-70 I 1.3965E-80 I 4.8456E-91 I 1.6813E-1011

I 5.9729E-02 I 5.9727E-02 I 5.9724E-02 I 5.9721E-02 I 5.9718E-02 I 5.9716E-02 I 5.9713E-02 I 5.9685E-02 1 5.9658E-02 I 5.9630E-02 I 5.9602E-02 I 5.9575E-02 I 5.9547E-02 1 5.9520E-02 1 5.9492E-02 1 5.9465E-02 1

4.6314€+00 4.6301 E+OO 4.6288E+00 4.6275E+00 4.6262E+00 4.6249€+00 4.6236E+00 4.6106E+00 4.5976E+00 4.5847E+00 4.5718E+00 4.5589€+00 4.5461E+00 4.5333E+00 4.5205E+00 4.5078E+00 1.5366E-02 I 1.5367E-02 I 1.5367E-02 I 1.5368E-02 I 1.5368E-02 I 1.5369E-02 1 1.5369E-02 I 1.5373E-02 I 1.5377E-02 I 1.5381E-02 I 1.5385E-02 I 1.5389E-02 I 1.5394E-02 I 1.5398E-02 I 1.5402E-02 I 1.5406E-02 1.5883E-01 I 1.5883E-01 1 1.5883E-01 1 1.5883E-01 I 1.5883E-01 I 1.5883E-01 I 1.5883E-01 1 1.5883E-01 I 1.5882E-01 I 1.5882E-01 I1.5881E-01 I 1.588lE-01 I 1.588OE-01 I 1.5880E-01 I 1.588OE-01 I 1.5879E-01 3.8732E-04 3.8732E-04 3.8732E-04 3.8732E-04 3.8732E-04 3.8732E-04 3.8732E-04 3.8732E-04 3.8732E-04 3.8732E-04 3.8732E-04 3.8732E-04 3.8732E-04 3.8732E-04 3.8732E-04 3.8732E-04

I1.3199E-01 I 1.3198E-01 I 1.3198E-01 I 1.3197E-01 I 1.3197E-01 I 1.3197E-01 I 1.3196E-01 I 1.3192E-01 I 1.3188E-01 I 1.3183E-01 I 1.3179E-01 I 1.3175E-01 I 1.3171E-01 I 1.3166E-01 1 1.3162E-01 I 1.3158E-01 I 3.4818E+01 1.5796€+01 7.1664E+00 3.2512€+00 1.4750E+00 6.6919E-01 3.0360E-01 1.1215E-04 4.1429E-08 1.5304E-11 5.6534E-15 2.0884E-18 7.7147E-22 2.8498E-25 1.0527E-28 3.8889E-32 1.8242€+00 1.8189E+00 1.81 37E+00 1.8085E+00 1.8033€+00 1.7981 E+OO 1.7929E+00 1.7421 E+00 1.6927E+00 l.W7E+00 1 S981 E+OO 1.5528E+00 1.5088€+00 1.4660E+00 1.4244E+00 1.3840~+00

13.2532E+00] 3.23~3E+00~3.2236E+00~3.2089E+00~3.1944E+00~ 3.1799E+OOl3.1656E+OO( 3.0272E+00~2.8976E+00~2.776OE+OO~ 2.6619E+00] 2.5545E+OOl2.4534E+OO I 2.3581E+00 I 2.2680E+00 I 2.1828E+00 1 1.8042€+01 1.5371E+01 1.3096E+Ol l.l158E+01 9.5062E+00 8.0991E+00 6.9002E+00 1.3905E+00 2.8020E-01 5.6463E-02 1.1378E-02 2.2928E-03 4.6202E-04 9.3101E-05 1.8761E-05 3.7805E-06 7.9180E-06 4.8431E-06 2.9623E-06 1.8119E-06 1.1082E-06 6.7785E-07 4.1461E-07 3.0386E-09 2.2269E-11 1.6321E-13 1.196lE-15 8.7663E-18 6.4247E-20 4.7085E-22 3.4508E-24 2.5290E-26 2.293OE-01 2.2715E-01 2.2502E-01 2.2292E-01 2.2083E-01 2.1876E-01 2.1671E-01 1.9726E-01 1.7955E-01 1.6344E-01 1.4877E-01 1.3541E-01 1.2326E-01 1.1219E-01 1.0212E-01 9.2957E-02 3.8608E-06 8.3854E-08 1.8213E-09 3.9557E-11 8.5917E-13 1.8661E-14 4.0530E-16 9.4686E-33 2.2121E-49 5.1678E-66 1.2073E-82 2.8205E-99 6.5892E-116 1.5394E-132 3.5962E-149 8.4015E-166 2.1524E-03 2.1349E-03 2.1176E-03 2.1004E-03 2.0833E-03 2.0664E-03 2.0496E-03 1.889lE-03 1.7412E-03 1.6048E-03 1.4792E-03 1.3633E-03 1.2566E-03 1.1582E-03 1.0675E-03 9.8387E-04 5.94OOE-04 5.8541E-04 5.7695E-04 5.6861E-04 5.6039E-04 5.5228E-04 5.4430E-04 4.7054E-04 4.0678E-04 3.5165E-04 3.0400E-04 2.6280E-04 2.2719E-04 1.964OE-04 1.6979E-04 1.4678E-04

14.5468E+00l3.osOsE+00l 2.3699E*0011.9909E+OOl 1.7689E+Oo/ 1.6251E+00~1.5231E+00~1.1345E+Oo~ 1.0475E+OO~I.O180E+00~ l.W07E+OOl 9.8629E-01 I 9.7JOOE-01 I 9.603BE-01 I 9.4832641 I 9.3675E-01 1

__

OFFICE OF CIVILIAN RADIOACTIVE WASTE MANAGEMENT 1. Q A QA SPECIAL INSTRUCTION SHEET +Psak

‘1 -1s-0 I . Page: 1 of: 1

Complete Only Applicable Items n A i ~ 2

7. Document Number@) CAL-WIS-TH-000012

This is a placeholder page for records that cannot be scanned. u

2. Record Date I 3. Accession Number

8. Version Designator REV. 00

07/19/200 1

4. Author Name(s)

9. Document Type DATA

ADAM SCHN~EDER I ..

10. Medium CD-ROM

1 6. TitldDescription THERMAL EVALUATION OF THE FORT SAINT VRAIN CODISPOSAL WASTE PACAKGE

@ 12. Traceability Designator DC #28747

13. Comments “7 -1 8 -4 1

€@e THIS IS A SPECIAL PROCESS CD-ROM, AS PART OF ATTACHMENT 1, THIS DATA SUBMITTAL TO THE RECORDS PROCESSING CENTER IS FOR ARCHIVE PURPOSES ONLY, AND IS NOT AVAILABLE FOR VIEWING OR REPRODUCTION

’-1 7.1 Q. 1 Rev. 04/30/20C

OFFICE OF CIVILIAN RADIOACTIVE WASTE MANAGEMENT QA: NIA

ELECTRON IC FILE C ERT I F ICATION

6. DATE LAST MODIFIED:

Thermal Evaluation for the Fort Saint Vrain Codisposal Waste Package 2. IDENTIFIER (e.g., DI OR PI): 3. REVISION DESIGNATOR:

7. NATIVE APPLICATION: (i.e., EXCEL, WORD, CORELDRAW)

8. FILE SIZE IN KILOBYTES:

Rev. 00

4. PDF FILE SUBMITTED: CAL- WIS-TH-0000 12

0 YES NO ATTACHED SOFTWARE FILE INFORMATION 5. ELECTRONIC SOURCE FILE NAME WITH FILE EXTENSION PROVIDED BY THE SOFTWARE:

None

LICENSE ISSUES)

None

OGl251200 1 I MS Word I 4,187kb 9. FILE LINKAGE INSTRUCTlONSllNFORMATION:

16 DOCUMENT OWNER (Print and Sign)

Adam K. Scheider fldjAt H X 4 J h 18 ORGANIZATION 19 DEPARTMENT 20 LOCATlONlMAlL STOP

MS 42311030K BSC Thermal 22 SUBMITTED BY (Print and Sign)

DaynettD Vosicky ~

Standard 10. PRINTER SPECIFICATION (LE., HP4SI) INCLUDING POSTSCRIPT INFORMATION (i.e., PRINTER DRIVER) AND PRINTING PAGE SETUP: (i.e., LANDSCAPE, 11 X 17 PAPER)

17 DATE

-l l / S / z m / 21 PHONE

295-4602 23 DATE

295-4496

lAI-dx:ope 1 I X I 7 > 8 i/a ) ( I / IcLiKewc'- /- r>b4 1 - i 3 - 0 :

HP 5Si Landscape for Attachments 11. COMPUTING PLATFORM USED: (i.e., PC, SUN, WIN 95, NT. HP)

& Pa e 3 & 4wf Attach. 5 aA-kd-7, All other attachments are portrait on 8 112 x l 1 Paper 12. OPERATING SYSTEM AND VERSION: (i.e., WINDOWS UNIX, SOLARIS)

d a ( -

24 DATE RECEIVED

7/6/2@,

PC# 110765 I IBM Compatible 13. ADDITIONAL HARDWARUSOFTWARE REQUIREMENT USED TO CREATE FILE(S): I 14. ACCESS RESTRICTIONS: (COPYRIGHT OR

25 DATE FILES TRANSFERRED 26 DCNO

r17- / ? - a m / dbrgv 27 NAME (Print and Sign)

hwi3 k?/GC/LCJL' / /

COMMENTSlSPEClAL INSTRUCTIONS

28 DATE

LJY -/ 7 - 2-04

15. IS SOFTWARE AVAllABLE FROM SOFTWARE CONFIGURATION MANAGEMENT? YES 0 NO SOFTWARE MEDIA TRACKING NUMBER N/A

NOTE: The software product(s) to develop this document are Commercial-Off-The-Shelf (COTS) software products which require no Software Media Number (SMN). The COTS software products are under Software Configuration Management (SCM) control.

OFFICE OF CIVILIAN RADIOACTIVE WASTE MANAGEMENT I. CIA: …/67531/metadc739081/m2/1/high_re… ·...

Documents

Transcript of OFFICE OF CIVILIAN RADIOACTIVE WASTE MANAGEMENT I. CIA: …/67531/metadc739081/m2/1/high_re… ·...