UNIVERSITÀ DI PISA GRUPPO DI RICERCA NUCLEARE – SAN PIERO A GRADO (GRNSPG) Any reproduction,...

UNIVERSITÀ DI PISAUNIVERSITÀ DI PISAGRUPPO DI RICERCA NUCLEARE – SAN PIERO A GRADO GRUPPO DI RICERCA NUCLEARE – SAN PIERO A GRADO

(GRNSPG)(GRNSPG)

Any reproduction, alteration, transmission to any third party or publication in whole or in part of this document and/or its content is prohibited unless the University of Pisa – San Piero a Grado Nuclear Research Group has provided its prior and written consent. This document and any information it contains shall not be used for any other purpose than the one for which they were provided. Legal action may be taken against any infringer and/or

any person breaching the aforementioned obligations.

3D nodalization performances of 3D nodalization performances of MASLWR ITF by RELA5-3D©v2.4.2 MASLWR ITF by RELA5-3D©v2.4.2

codecode

2010 RELAP5 International User’s Seminar2010 RELAP5 International User’s SeminarWest Yellowstone, Montana

September 20-23, 2010 September 20-23, 2010

Title 3D nodalization performances of MASLWR ITF by RELA5-3D©v2.4.2 code

Authors A. Del Nevo, C. Parisi, F. D'AuriaRevision/Date

0 20 09 2010

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Any reproduction, alteration, transmission to any third party or publication in whole or in part of this document and/or its content is prohibited unless the University of Pisa – San Piero a Grado Nuclear Research Group has provided its prior and written consent. This document and any information it contains shall not be used for any other purpose than the one for which they were provided. Legal action may be taken against any infringer and/or any person breaching the aforementioned obligations.

3D nodalization performances of MASLWR ITF by RELA5-3D©v2.4.2 code

2010 RELAP5 International User’s Seminar2010 RELAP5 International User’s SeminarWest Yellowstone, Montana – September 20-23, 2010

List of content INTRODUCTORY REMARKS

MASLWR ITF FACILITY

OBJECTIVE OF THE ACTIVITY

NODALIZATIONS DEVELOPED

QUALIFICATION OF THE NODALIZATION

THE EXPERIMENTAL DATA

SIMULATIONS OF MASLWR TESTS 002 AND 003A

IAEA ICSP ON MASLWR

CONCLUSIVE REMARKS

2/23

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Introductory remarks S. M. Modro, J. E. Fisher, K. D. Weaver, J. N. Reyes Jr.,

J. T. Groome, P. Babka, T. M. Carlson, Multi-Application Small Light Water Reactor Final Report, INEEL/EXT-04-01626, December 2003

The Multi-Application Small Light Water Reactor (MASLWR) project was conducted under the auspices of the Nuclear Energy Research Initiative (NERI) of the U.S. Department of Energy (DOE).

Objectives were:

to develop the conceptual design for a safe and economic small, natural circulation light water reactor,

to address the economic and safety attributes of the concept, and

to demonstrate the technical feasibility by testing in an integral test facility

3/23

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Introductory remarks Features of the concept design:

The reactor core and the SGtube bundles inside the vessel

No main primary system piping

Buoyancy forces driving head for primary coolant flow

RPV inside a steel containment vessel filled with water passive ultimate heat sink

4/23

5 years for refueling and maintenance performed by removing the entire module

Test prgram with ITF (MASLWR) has been executed at Oregon State University (OSU)

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Introductory remarks Nuscale Power formed in 2007 with tech-transfer agreement from

OSU and privately funded

NuScale technology developed and tested by Oregon State University, based on OSU, INL and Nexant (Bechtel) DOE NERI program for MASLWR

NuScale Power is commercializing a 45 MWe natural circulation PWR module that can be scaled to meet customer requirements of virtually any size

Base Design is a 12-Module, 540 MWe plant

Designed to meet NuScale Customer Advisory Board

Utility Requirements for near-term deployment in the USA

Seeking US-NRC Design Certification

NuScale Project Organization

5/23

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Oregon State University MASLWR ITF Integral test facility

Scaling

1:3 length

1:254.7 volume

1:1 time scale

Characteristics

Full pressure (11.4 MPa)

Full temperature (590 K)

Fuel rods eclectically heated

Maximum power 398 kW (7.1 kW per 56 rods)

6/23

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Oregon State University MASLWR ITF

It simulates the primary system

the secondary system

the containment system

the water pool

7/23

Containment

Water pool

Primary system Details of the helical-coils SG

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Oregon State University MASLWR ITF Four tests are documented (full set of experimental data not

available)

OSU-MASLWR-001: Inadvertent actuation of 1 submerged ADS valve

OSU-MASLWR-002 & 003A: Natural circulation with core power up to 210kW (used to set up the nodalizations for ICSP participation)

OSU-MASLWR-003B: Inadvertent high containment ADS vent line actuation

8/23

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Use of RELAP5-3D at GRNSPG/UNIPI


Objective of the activity GRNSPG participation in the IAEA International Collaborative

Standard Problem (ICSP) on Integral PWR Design Natural Circulation Flow Stability and Thermo-hydraulic Coupling of Containment and Primary System during Accidents

Validation of RELAP5-3D v2.4.2 applicability in modeling integral PWR

Explore thermal-hydraulic and modeling challenges for new small design PWR

3D vs. 1D modeling (in SPF & TPF conditions)

Assessment/accuracy of current TH/SYS (i.e. RELAP5-3D v2.4.2) performance in predicting

HEX in helical coils SG

Choked flow & coupled containment pressurization

NC flow instabilities at reduced mass inventories

Condensation

9/23

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Nodalizations developedGeneral features of the nodalizations

Two independent nodalizations were set up

1D nodalization, which can be run with RELAP5-3D v2.4.2, RELAP5/Mod3.3 (and TRACE code) and 3D nodalization by RELAP5-3D v2.4.2

All relevant parts of the MASLWR ITF are modeled

3 equivalent SG helical-coil tubes (1 for each tube group length)

1 equivalent SG helical-coil tube

The maximum pipe node to node length ratio adopted is 1.2

Sliced nodalization approach

HF option activated chocked flow

Absolute and relative elevations maintained as in facility description

MULTID components (3D nodalization)

3D momentum equations used

10/23

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Nodalizations developed: 1D nodalization 1D nodalization, which can be run with RELAP5/Mod3.3

(and TRACE code)

Reactor coolant system (3 pipe and 2 branch) 41 axial nodes

Secondary system (2 tmdpvol, 1 tmdpjun, 2 vlv, 2 branch, 3 pipe)

High pressure containment vessel (3 pipe, 2 branch, 1 vlv, 1 tmdpjun)

48 axial nodes

Cooling pool vessel (2 pipe and 2 branch)

56 axial nodes

Automatic depressurization systems

Blowdown lines (2 pipe, 2 vlv, 1 branch)

Vent lines (2 pipe, 2 vlv, 1 branch)

Sump return lines (2 pipe, 2 vlv, 1 branch)

11/23

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Nodalizations developed: 3D nodalizationRELAP5-3D COMPONENTS

REACTOR COOLANT SYSTEM

1 MULTID COMPONENT

SECONDARY SYSTEM

2 TMDPVOL, 1 TMDPJUN, 2 VLV, 2 BRANCH, 5 PIPE

HIGH PRESSURE CONTAINMENT VESSEL

1 MULTID COMPONENT, 1 PIPE, 1 VLV, 1 TMDPJUN

COOLING POOL VESSEL

1 MULTID COMPONENT

AUTOMATIC DEPRESSURIZATION SYSTEMS

1. BLOWDOWN LINES (2 PIPE, 2 VLV, 1 BRANCH)

2. VENT LINES (2 PIPE, 2 VLV, 1 BRANCH)

3. SUMP RETURN LIENS (2 PIPE, 2 VLV, 1 BRANCH)

12/23

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Nodalizations developed: 3D nodalization

REACTOR COOLANT SYSTEM (MULTID)

2 radial; 8 azimuthal, 42 axial

672 volumes

Leaning MULTID Leaning TOWER

13/23

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HL REGION

HL REGION

(w/ area reduction)

UP

SUMP RETURN (340)

UP

HL REGION

(reduced area)

PRZ

UP

UP

SG

UP

SG

CL

CORE REGION

UPDC

CL

DC

UP

UP

FW inlet (210-220-230)

SL outlet (210-220-230)

ADS VENT (300)

BLOWDOWN (320)

PRZ plate

Grid wires

Upper grid wires

Core flow plate

Sect. A-AAA

Heaters

3 parallel pipes

3 parallel pipes

14/23

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HPC (MULTID)


384 volumes

CPV (MULTID)


224 volumes


RUPTURE DISK (410)

SUMP RETURN (340)

BLOWDOWN (320)

ADS VENT (300)

HPC

CPV

15/23

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NC tests (002 and 003A) with core power up to 210kW

Results provided during the 1st ISCP meeting at OSU 15-18 March 2010

Nodalization qualification: the experimental data

16/23

10

12

14

16

18

20

22

24

26

28

30

0 500 1000 1500 2000 2500 3000

DT

(K)

Time (s)

Core DT

Test -002

RELAP

ΔT across the core presented by B. Woods: Test 002

Specifications according with INEEL/EXT-04-01626, Dec. 2003

10

15

20

25

30

35

40

0 100 200 300 400 500 600 700 800 900 1000

DT

(K

)

Time (s)

Core DT

Test -003A RELAP

ΔT across the core presented by B. Woods: Test 003A

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Nodalization qualification: simulations of MASLWR Tests 002 and 003A

17/23

50

80

110

140

170

200

230

0 500 1000 1500 2000 2500 3000 3500 4000 4500

Pow

er [k

W]

Time [s]

OSU MASLWR Tests 002 and 003A - RELAP5-3D v2.4.2: power exchanged in SG secondary side

EXP - Core powerEXP - Calculated (primary coolant DT)EXP - Calculated (secondary coolant DT)R5-3D - Secondary side

Primary pressure 7.7 MPa

Power

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15

18

21

24

27

30

0 500 1000 1500 2000 2500 3000 3500 4000

Tem

pera

ture

[K

]

Time [s]

OSU MASLWR Tests 002 and 003A - RELAP5-3D v2.4.2: ΔT across the core

EXP

R5-3D



ΔT across the core vs time

18/23

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19/23

60

70

80

90

100

110

120

130

0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0

Flow

[l/m

in]

Power [kW]

OSU MASLWR Tests 002 and 003A - RELAP5-3D v2.4.2: core volumetric flow rate

EXP

R5-3D


core volumetric flow rate vs time

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20/23

450

460

470

480

490

500

510

520

530

540

550

0 500 1000 1500 2000 2500 3000 3500 4000

Tem

pera

ture

[K]

Power [kW]

OSU MASLWR Tests 002 and 003A - RELAP5-3D v2.4.2: SG outlet coolant temperature secondary side

EXP

R5-3D


SG outlet coolant temperature secondary side

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IAEA ICSP on MASLWR The ICSP is divided into two separate tests.

The first test involves a stepwise reduction in primary coolant volumetric inventory in the MASLWR test facility while operating at decay power.

21/23

B. G. Woods, M. R. Galvin, C. J. Bowser, Problem Specification for the IAEA International Collaborative Standard Problem on Integral PWR Design Natural Circulation Flow Stability and Thermo-hydraulic Coupling of Containment and Primary System during Accidents, OSU-ICSP-10001, Augusto 2010

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IAEA ICSP on MASLWR The ICSP is divided into two separate tests (cont’ed)

The second test involves a loss of FW transient with subsequent ADS blowdown and long term cooling.

22/23

B. G. Woods, M. R. Galvin, C. J. Bowser, Problem Specification for the IAEA International Collaborative Standard Problem on Integral PWR Design Natural Circulation Flow Stability and Thermo-hydraulic Coupling of Containment and Primary System during Accidents, OSU-ICSP-10001, Augusto 2010

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Use of RELAP5-3D at GRNSPG/UNIPI


Conclusive remarks The nodalization is developed and set up and ready for the

participation in the ICSP (submission of the pre-test results by the end of December 2010)

GRNSPG/UNIPI will participate with RELALP5-3D v2.4.2

RELAP5/Mod3.3 and TRACE code might be used depending upon the working resources

Performances of the code RELAP5-3D v2.4.2 are presented

The activity is still in progress

23/23

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