JAERI-Data Code96-005 JAKKI - Da t n/Cada—CKf-005

EXPERIMENTS ON IRON SHIELD TRANSMISSION OFQUASI-MONOENERGETIC NEUTRONS GENERATED

BY 43-AND 68-MeV PROTONS VIA THE 7Li(p,n) REACTION

March 1996

Hiroshi XAKASHIMA, Noriaki XAKAO'1, Shun-ichi TAXAKATakoMhi NAKA3IUKA*' Kazuo SHIN"' Susumu TANAKA

Shin-Ichiro MEKJO, Yoshihiro XAKANE, Hiroshi TAKADAYukio SAKAMOTO and Mumoru IIABA'1

Japan Atomic Energy Research InstituteVOL 2 7 H S 1 7

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Thi\ report i% issued irregularly.

Inquiries about uvuilability of the report", should be addressed to Information Division.

Department of Technical Information. Japan Atomic Hncrgy Research Institute. ToLii-

mura, N;ik:i-gun. lb.ir;iki-ken 319-11. Japan.

©Japan Atomic MniT^y Hr>.sonnJ» Institute, 19%

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JAKHI-Dutn/Cwlif i)fl-U05

Experiments on Iron Shield Tranamlasion of Quaai-monoenergetio Neutrons

Generated by '13- and 68-MoV Protons via the 7Li(p,n) Roaotion

Hiroshi NAKASHIMA, Noriaki NAKAO", Shun-ichi TANAKA+ , Takashi NAKAMURA*2

Kazuo SHIN*3, Suaumu TANAKA+\ Shin-ichiro MEIGO, Yoshihiro NAKANE

Ifiroshi TAKADA, Yukio SAKAMOTO and Mamoru BABA*4

Department of Reactor Engineering

Tokai Research Establishment,

Japan Atomic Energy Research Institute

Tokai-mura, Naka-gun, Ibaraki-ken

(Received February 7, 1996)

In order to provide benchmark data of neutrons transmitted through iron

shields in the intermediate-energy region, spatial distributions of neutron

energy spectra and reaction rates behind and inside the iron shields of

thickness up to 130 cm were measured for '»3- and 68-MeVp-7Li neutrons using a

quasi-monoenergetic neutron beam source at the 90-MV AVF cyclotron facility of

the TLARA facility in JAERI. The measured data by five kinds of detectors: the

BC501A detector, the Bonner ball counter, 2 3 8U and 232Th fission counters, 7LiF

and n " L i F TLDs and solid state nuclear track detector, are numerically

provided in this report in the energy region between 10""1 eV and the energy of

peak neutrons generated by the 7Li(p,n) reaction.

Keywords: Iron, Benchmark Experiment, Transmission, Quasi-monoenergetic Neutron

Beam Source, Intermediate Energy, Neutron Spectrum, Neutron Reaction

Rate, Neutron Dose Equivalent

This research report is the result of the joint study with University of Tokyo,Tohoku University and Kyoto University.• Office of Planning•• Advanced Radiation Technology Center, Takasaki Radiation Chemistry Research

Establishment•l University of Tokyo, Institute for Nuclear Study** Tohoku University, Cyclotron and Radioisotope Center•3 Kyoto University•' Tohoku University

.JAKHI-lJHlu/Codo 1)6-006

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Contents

1. I n t r o d u c t i o n ••••• ••••" - • ••"" 1

2. Experiment • • •• 3

2.1 TIARA Facility and Experimental Sot Up 3

2.2 Neutron Sources 3

2.3 Detectors and Data Analysos for Shielding Experiment 4

2.3.1 BC501A Liquid Scintillation Counter \

2.3.2 Bonnor Ball Counter • •••••• •"• 5

2.3.3 Fission Counters •••• 5

2.3.4 Thermolumine3cent Dosimeter(TLD) 0

2.3.5 Solid Stato Nuclear Track Doteotor(SSNTD) 6

3. Results •"- - 7

3.1 Neutron Spectra in tha Energy Region above a fe« MeV Measured by

the BC501A Detector 7

3.2 Neutron Reaction Rates and Spectra in the Energy Region Up to a

Few MeV Measured by the Bonner Ball Counter "7

3.3 Neutron Reaction Rates Measured by Fission Counters, TLDs and SSNTD -••• 7

3.4 Neutron Dose Equivalent 8

4. Summary • • 9

Acknowledgements 9

References 10

JAKUI-Dntn/CVido 9B-005

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1, INTRODUCTION

Intermediate- and high-energy accelerators arc recently planed and constructed for

utilization in various fields: physical, engineering and medical use. With increasing the energy

and intensity of accelerated particles, the neutrons generated by the particles have strong

penetrability and the facility requires more massive shields. In the facilities sophisticated shielding

designs arc required to keep regulations for the dose limit and to prevent from activations of

devices as well as to save the building cost. Several codes and code systems have been developed

to achieve the suitable shielding design.1'2'3 The codes arc, however, designed for the particle

transport calculation in the energy region above 100 McV. On the other hand, the neutron

transport calculation in intermediate-energy region between 20 and 100 McV is the most crucial

part on accelerator shielding, because nuclear reactions arc complex. Therefore, the validity of

the calculation methods should be confirmed by benchmark experimental data on the neutron

transmitted through the bulk shields in the energy region.

A few neutron spectra behind the bulk shield have been measured for neutron source in

the intermediate energy region.4'5'67 Shin and Uwamino's measurements have used source

neutrons of broad energy spectra generated via the C(p,n) reaction by 52-McV proton and the

Cu(p,n) reaction by 65-McV proton. Ishikawu ct al. have measured the transmitted spectra

along the beam axis for quasi-monocncrgctic source neutrons generated via the 7Li(p,n) reaction

by 25- and 35-McV protons.

A quasi-monocncrgctic neutron field using the 7Li(p,n) reaction was recently established

at the 90-MV AVF cyclotron facility of the TIARA (Takasaki Ion Accelerator for Advanced

Radiation Application) facility in JAERI (Japan Atomic Energy Research Institute), where

neutron beam is served for shielding experiments. In the neutron field we can study the clastic

and inelastic scattering reactions respectively by using the quasi-monocncrgctic neutrons, and

investigate the angular distribution of the scattering reaction by using neutron beam and measuring

spacial neutron distribution transmitted through shields.

In this study, iron was chosen as a shielding material, because iron was often used for

massive shields around beam dumps and targets, and monogenctic material was effective for

investigating the nuclear reaction. The spatial and energy distributions of neutrons transmitted

through iron shields were measured using source neutron beam generated via the 7Li(p,n)

reaction by 43- and 68-McV protons. The objective is to provide benchmark data of neutrons

- 1 -

.JAHRI-n/iln/Cod(j Wi-OOfi

transmitted through iron .shields for investigating the accuracy of calculation codes and crosssection data libraries.

- 2 -

00-000

2. EXPERIMENT

2.1 TIARA facility and experimental set up

The experiment was carried out at the AVF cyclotron facility of the Takasaki site at

JAERI, which had a neutron beam course, LC-coursc, arranged for the neutron shielding and

cross section experiments. The cross sectional view is shown in Fig.l, The neutron generated

at the accelerator room passed to the experimental room (the 3rd light-ion room) through a

10.9-cm-diam. x 225-cm-long iron collimator embedded in a concrete wall. The collimator

is used as a rotary beam shutter, through which the neutron beam was injected into the shield

when the shutter was open, as shown in Fig.l. The iron shield of 10 to 130 cm thickness was

assembled by 120 cm x 120 cm by 10-cm-thick slabs and was fixed on a movable stand to set

in contact with the collimator exit located at 4 m from the neutron target. The additional

collimator shown in Fig.2 were used only for off-center measurements with thinner shield: 10-,

20- and 40-cm-thick iron, in order to depress the contribution of neutrons leaked through filler

of iron ball and iron sand or rotary shutter of iron and polyethylene which includes low density

space of air gap in the concrete wall. The additional iron collimator was composed of 120 cm

x 120 cm slab of 10 cm thickness with a 10.9-cm-diam. cylindrical hole equal to that of the

rotary shutter collimator. The combination of the shield and additional collimator arc given in

Table 1, and the atomic compositions of iron shield, additional iron collimator and the concrete

wall arc tabulated in Table 2.

2.2 Neutron sources

The source neutrons were generated by 43- and 68-McV protons bombarding

3.6-mm-thick and 5.2-mm-thick, 99.9 % enriched 7Li targets, respectively, in the target

chamber in the accelerator room. The protons penetrated the target with the 2-McV energy loss

were bent down toward the beam dump by the clearing magnet. The beam dump consists of 30

cm x 30 cm x 50 cm hole surrounded by iron in the concrete wall as shown in Fig.l. The neutrons

produced in the forward angle can reach the experimental room through the collimator.

The spectra of quasi-monocncrgctic neutron source were measured with a BC501A liquid

scintillation counter using the time of flight (TOF) method. The block diagram of the measuring

electronic circuit is shown in Fig.3 for the TOF measurement. The detector was placed about

14 m away from the target, and the repetition periods of the proton beam from the cyclotron:

_ o

JAKKf-DiiUi/Coilo 5)0 OOfi

15,460 and 18.919 MHz, were extended to one seventh by beam choppers In order to measure

the neutron spectra down to a few McV. The efficiency of the scintillator for the TOF

measurement was obtained from the measured response matrix". The measured source neutron

energy spectra are shown in Fig. 4 and tabulated in Tables 3 and 4.

The absolute Hux of source nculrons in the monocncrgctic peak per proton beam charge

(/iC) has been measured by a proton-rccoil-countcr-tclcscopc (PRT) set at the position of 5.54

m from the targct.g The neutron fluxes in the monocncrgctic peak measured by the TOF method

were normalized by the absolute value measured by PRT.

During the experiment, the number of protons incident on the Faraday cup was measured

using the current integrator connected to the Faraday cup In the beam dump. The range of proton

currents in this experiment was 0.5 nA to 3 mA. The counts of two neutron flucncc monitors

(2ii\J and l12Th fission counters) placed near the target were normalized to the absolute peak

nsulron flux through the amount of total charges of proton beam, and were used for calculating

the real total proton charges even in the low beam current runs in order to reduce the uncertainty

of dark current on the Faraday cup.

2.3 Detectors and data analyses for shielding experiment

For the shielding experiment five kinds of detectors were applied for the measurement

of neutron spectra and reaction rates behind and inside the iron shields. The detectors used for

the iron shielding experiment and the measured positions arc summarized in Table. 1.

2.3.1 BC501A liquid scintillation counter

One of the neutron spectromctry in the shielding experiment was performed with the

12.7-cm-diam. x 12.7-cm-long DC501A organic liquid scintillator (Bicron Co. Ltd.) coupled

to a R4143 photomultiplicr (Hamamatsu Photonics. Co. Ltd.). The block diagram of the

measuring electronic circuit for the shielding experiment is also shown in Fig.3. The rise-time

pulses which distinguished between neutron-cvent and photon-cvent were supplicJ by the

risc-rimc-to-hcight converter (OHYO KOKEN KOGYO Co., Ltd.). In the shielding

experiment, the two pulses of pulsc-hcight and rise-time were recorded in cvcnt-by-cvcnt

mode. These data were taken by the ND9900 MPA 8/16 (CAMBERRA Co. Ltd.) and the VAX

STATION 3100 (DEC Co. Ltd.), then recorded in a hard disk.

• JAKIU- i)/it/i/C(i(l(- 00--OOfi

Tlic cvent-by-cvent data measured with 13C501A were converted to two dimensional

distribution of pulse-height and rise-time, mid the pulse-height distributions induced by

neutrons were selected by eliminating the y-ray pulses, Then they were converted into the

neulron energy speclra using the FERDOU unfolding code10 and the measured response matrix".

The energy calibration of the light output pulses was performed using the Compton edge of

4.43-McV y-rays from a wlAm-Bc source and the recoiled proton edge of 40- or 65-McV

monocnergetic neutron peak of 43- or fih-MeV p-Li reaction fitted to the calibration values

from Rcf.[K], and using the zero point with a Research Pulscr. The dead time correction of the

data taking system was done from the difference of the number counted in the sealer and the

number of events which were recorded in the hard disk. Finally the absolute values of the

transmitted spectra are presented as the flux per proton beam charge (jiQ which can be estimated

from the flucnce monitor counts.

2.3.2 Bonner ball counter

Multi-moderator spectrometer, Bonncr ball, with four spherical polyethylene moderators

of 1.5, 3.0, 5.0 and 9.0 cm thicknesses and without moderator was also used for the shielding

experiment. The thermal neutron detector inserted in the center of the moderator is a

5.0H-cm-diam. spherical proportional counter, made by LND Inc., filled with 10 atm (at 22 )3Hc gas. The pulse height spectra for five different moderators of the Bonncr ball counter were

recorded.

The pulse height data measured with the Bonncr ball counter were summed up to get

counts above the y-ray discrimination level. These five counts measured for five moderators

were unfolded with the SAND-2 code" and the response matrix given by Uwamino ct al12. The

response matrix is shown in Fig. 5 and given in Table 5. Initial guess spectra used in unfolding

were obtained from the MORSE13 calculations with the H1LO86 group cross section set14 at each

measured position. We then obtained the spectra of neutrons in the energy range from K)"4 cV

to the peak energy.

2.3.3 Fission counters

^"U and a2Th fission counters (Ccntronic FC480/10U0) with a 10.1-cm-longx 3.81-

cm-diam. active volume were used for measuring neutron reaction rates behind the iron shield.

- 5 -

.IAKM

tetenejes wcrc calibrated by the mCispontaneous fission neutron source of

Facility «f Radiation StunUtifd (FK8)15 of JAKRI, 'Hie facility l« the .wewml hiundurd field of

neutron, The neutron source ImU an intensity of 1.218 x \(f n/*cc with the uncertainty of ±3%.

The measured efffdenefefr are M>5 * I01 ami 1>M> n H? b&m/em*/&MM» (±4 uml 3,4%)f

respectively. The rtsslort cross sections of m\J tintl M2Th have been evaluated up to 20 McV in

JENDL~y\ tneusuted by Liwnvski el »),'•'* in Ihc energy region between 20 and 400 McV and

calculated using the IIIiTC code above 400 McV, The cross sections arc shown in Fig. (»and

the group cross section data are given in Table (u

2.3.4 Thcrmolumincsccnt dosimeter (TLfl)

Neutron reaction rates were measured on the axis of the beam in the iron shield using

"iWimil M<JJ TU>¥(JJWMMW V.th Ud,) of ] s 1 x 6 nmi\ Thez/noJumluesccncc wiwfc«tl t)ut

by a TLD reader (f ianhaw 2(KK)), and converted to the absolute dose in TLDs using a calibration

factor determined with'"Co y-ray.s of I KS within the uncertainty less than 3 %. The neutron

energy responses were calculated by a code developed by Ilashikura ct al. which was based on

a KliUMA calculation". The calculated neutron energy responses arc shown in Fig. 7 and

tabulated in Table 7.

2.3.5 Solid state nuclear track detector (SSNTD)

The neutron reaction rales in ihc shield were also measured using a solid state nuclear

track detector: Types TS~luN resin manufactured by Fttkuvi Chemical Industry Co. Ltd. from

ti monomer (TS-1 OS) made by Tokuyama Soda Ltd. The composition of the detector is the same

m thai of CK-39 (Allyl tfiglyeo! cyiboiiuic). The detector Ls u iccujngulux solid of 10 x 5 x t

mm* attached with a polyethylene radiator of 1 mm thick. After Ihc exposed detectors were

etched chemically, the etch pits on the detectors were counted through the optical microscope

of 400 limc» magnifications. The neutron response was calculated by a Monte Carlo code system:

SSNRHS31. bstscd on the SCINFUL codcJl. The calculated neutron response is shown in Fig.

K and given in Table K.

,\A\''M\ -\)nln/CiHk< JKi-OOf)

3. KliSULTS

3.1 Neutron spectra in the energy region above n few MeV measured by the BC501A detector

Neutron spectra in the energy region above a few McV were measured just behind the

iron shield on the beam axis and at the off-center positions of 20 and 40 cm from the beam axis

as tabulated in Table 1 using (he BC501A detector. Figure 9 shows the measured neutron energy

spectra behind various thickness of iron up to 100 cm on the beam axis for 43-MeV p-Li

neutrons. The errors of the measurement in the figure include only errors of spectrum unfolding

and counting statistics in the measurement, neglecting that the source neutron flux has errors of

lJRT(3-5%), conversion factor of flucncc monitor to total charges of proton beam (3%), neutron

penetration factor through objects on the beam line (3%) and the flucnu monitor counting

statistics (less than 1%). The measured ncutruij spectra at the positions of 20 and 40 cm from

the beam uxJ.v behind ()-, 11)-, 20- and 40-cm thick .shields arc shown )n Figs, 10 through 13

for 43-McV p-Li neutrons, respectively, The measured neutron spectra for 6K-McV p-Li

neutrons arc also shown in Figs, 14 through 17 behind the iron shield of thickness up to 130 cm

on the beam axis and at the positions of 20 and 40 cm from the beam axis. The measured

neutron spectra arc also tabulated in Tables 9 through 20.

3.2 Neutron reaction rates and spectra in the energy region up to a few McV measured by the

Oonncr ball counter

Neutron reaction rates behind the iron shields up to 100 cm thick on the beam axis were

measured using the Bonncrball counter with four spherical polyethylene moderators of 1.5,3.0,

5.0 and 9.0 cm thicknesses and without moderator as given in Tables 21 and 22. Neutron spectra

obtained from the reaction rates using the SAND-2 unfolding code and the calculated response

matrix arc shown in Figs. 18 and 19 for 43- and 68-McV p-Li neutrons, and the numerical data

arc given in Tables 23 ad 24. The experimental errors of the Bonncr ball counter could not be

obtained since the SAND-2 unfolding code can not give them.

3.3 Neutron reaction rates measured by fission counters, TLDs and SSNTD

Fission reaction rates were measured behind the shields of various thicknesses on the beam

axis and at the position of 20 cm from the beam axis using ^"U and 2)2Th fission counters, as

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. / A M I - l)uln/V.t>(U> fXi OOfi

shown in Figs, 20 and 21, and given in Tables 25 and 26 for 43- and 68-MeV p-Li neutrons.

The uncertainties of the measured data shown in the figures include the counting statistics of

the fission counters and neutron intensity monitor. The reaction rates indicate the integrated

neutron flux in the energy region above the threshold energy of the fission reactions: about 1

MeV,

In Table 27 the differences of neutron reaction rates measured by 7LiF and hi"LiF TLDs

in the iron shield arc given for 43- and 6K-McV p-Li neutrons. The differences arc dominated

by the neutron in the energy region up to 1 MeV as shown in Fig. 7. The errors of the

measurements are the counting statistics of each detector and neutron intensity monitor.

The measured nculron reaction rales in the iron shield are shown in Fig. 22 and given in

Table 28 using SSNTD for 43- and 68-MeV p-Li neutrons. As shown in Fig. 8, the efficiency

of the deteclor is dominated by the neutron in the energy region up to about 10 MeV. The

uncertainties of the measurements include the counting statistics of etch pits and neutron

intensity monitor.

The combination of the reaction rates measurements covers the whole energy region up

to the energy of peak neutrons produced by the neutron source, and the results of these

measurements are effective to confirm the integrated neutron flux in each energy region.

3.4 Neutron dose equivalent

The neutron reaction rates measured by a rcm counter, made by the Fuji Co. Ltd. arc

tabulated in Table 29 as a reference of neutron dose equivalents. Neutron dose equivalents were

also estimated from the neutron spectra above 10 MeV measured by the BC501A detector and

the neutron spectra up to 10 MeV by the Bonncr ball counter by multiplying the 1CRP21

ncutron-flux-to-dosc conversion factor22, «s given in Table 30. The neutron dose equivalents

arc compared with the neutron reaction rates measured by the rcm counter in Fig. 23. The

measured reaction rates by the rcm counter arc lower than the evaluated values behind the iron

shield of 20 cm thickness, while higher behind the iron shield of 100 cm thickness. The

discrepancy is caused by the response function of the rcm counter. The detector docs not have

the same response function as the dose conversion factor in the energy regions above 20 MeV

and between a few hundred kcV and a few kcV.

_ a _

HO-OOfi

4. SUMMARY

The spatial distributions of neutron energy spectra and reaction rates behind and inside

the iron shields up io 130 cm were measured for 43- and fi8-McV p-Li neutrons, which cover

the energy region between K)"1 cV and the energy of peuk neutrons generated viu the 7Li(p,n)

reaction using five kinds of detectors: the BC501A detector, the Conner ball counter, aHU andl12Th fission counters, 7LiF and mLW TLDs and SSNTD.

The data measured absolutely were tabulated in this report in order to estimate the

accuracy of the calculation code and cross section data set in the intermediate energy region.

As shown in figures in this report, the energy spectra measured using the quasi-monocncrgctic

neutron source give useful information for investigating the clastic and inelastic scattering

reactions respectively, and the spatial distributions behind the iron shields obtained using neutron

beam arc valuable for studying the angular distribution of the scattering reaction. The

measurement in the wide energy range provided the neutron dose equivalents behind the Iron

shields due to the intcrmcdiatc-cncrgy neutrons.

ACKNOWLEDGMENTS

We wish to thank the operation staff of TIARA for the cyclotron operation. This work

has been supported by the Univcrsitics-JAERI Collaborative Project Research Program.

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JAUKI DiiUi/Cotlf.' % Mi

REI-'I-KENCKS

1. Cloth P., Filgc-H I)., Ncef R.I)., Stcracnlinch I), Ifcul Ch,, T, W, Armstrong T.W., Collxmi H.L,

I*. Anders B. and Iirucknuinn 11.: FA-IRE-K AN/12/88, "1IKNMES A Monte Carlo Program

System for Beam-Materials Interaction Studies" (1988).

2. Prael K.K. and Lichtcnstein !!.: LA-UK-fiP-.WH, "liSKK GI/IDK TO IX'S: Till* LAI1BT

COOK SYSTEM" (1980).

3. Nakahara Y. ami Tsutsu T.: JAKRI-M 82-198, "NMTC/JAERI A Simulation Code System for

High Energy Nuclear Reactions and Nucleon-Meson Transport Processes" (1982).

4. Shin K., Uwamino Y., Yoshida M,, Hyodo T, and Nakainura T.: "Penetration of Secondary

Neutrons and Photons from a Graphite Assembly Exposed to f)2~MeV Protons", Nud, Sci,

Kill!., 71,294 (197!)).

f>. Uwamino Y., Nakainura T. and .Shin K,: "Pc/ielration Through Shielding Materials of

Secondary Neutrons and Photons Generated by ,%-MeV Protons", Nucl. Sci, Knj;., 80, .')(>0

(1982).

(\. Shin K., fsliii Y., Miyaliani K., Uwarnirio Y., Sakai IL and Nurata T.: "Transmission of

Intennediate-Unertjy Neutrons and Associated (lamina Ways Through IRON, Lead, Graphite

and Concrete Shields", Nucl. Sci. ling., 109, 380 (1091).

7. Ishikawa T., Miyatna Y. and Nakaimira T.: "Neutron Penetration Through fron and Concrete

Shields witli Uie Use of 22.0- and .'12.!5-MeV (Juasi-Monoenergetic Sources", Nucl, Sci.

Bng., 11(5, 278 (199-1).

8. Haha M., Kiyosumi T., Iwasaki T., Yoshioka M., Matsuyatna S., Hirakawa N., Nakatmira T.,

Tanaka Sti., Tanaka R., Tan.ika Sh., Nakashinia If. and Mcijjo S.: JAHRI-M 94-019, p.200,

"Characterization and Application of 20-90 MeV ' Li(p,n) Neutron Source at TIARA" (1994).

9. Shin K., Uwamino Y. and llyodo T.: "Propagation of Krrors from Response functions to

Unfolded Spectrum", Nucl. Techno!., 53, 78 (1981).

10. Nakao N., Nakamura T., Iiaha M., Uwimitio Y., Nakanishi N., Nakashima II. and Tanaka S.:

"Measurements of Response Function of Organic Liquid Scinu'llator for Neutron Hnergy Range

up to 135 MeV", Nucl. Instnim. Methods, Wl, 454 (1995).

11. Mcelroy W.N., lierg S., Crokctt T. and Hawkins R.G.: AFWL-TR-67-41, Vols. 1 through 4,

Air Force Weapons Laboratory, "A Computer Automated Iterative Methods for Neutron Flux

Spectra Determination by Foil Activation" (1907).

12. Uwamino Y., Nakamura T. and Mara A.: "Two Types of Multi-Moderator Neutron

Spectrometers: Gamma-Ray Insensitive Type and High-Efficiency Type", Nud. Instnim.

Methods in Phys. Res., A2W, 299 (1985).

13. Straker K.A., tevens P.N., Irving D.C. and Cain V.R.: ORNL-4585, "The MORSE Code -A

Multi-Group Neutron and Gamma-Kay Monte Carlo Transport Code" (1970).

14. Alsmillcr R.G. Jr., Uames J.M. and Drischler J.D.: ORNL/TM-9801, "Neutron-Photon

- 1 0 -

o flfi-OOf)

Multigroup Cross Sections for Neutron Energies <4()0 McV (Revision 1)" (1980).

lfi. YoshisKiwa M.: private comtriunication,

l(j, Shibata K, ct nl.: JAERf VM9, "Japanese Evaluated Nuclear Data Library, Version-.'?

-JKNDL-H-" (1990).

17. Usowski P.W. ct at.: "Neutron fadueecl fission Cross Section Kates for "" 'Hi , »* ' » » u ,2 J ' N p and " ' P u from 1 to 400 McV", I'roc. Int. Conf. Nuclear Data for Sci. and Techno!.,

Mito, Japan, p.97-99 (1088).

18- Lisow.ski P.W. el al.: "Fission Cross Sections in the Intermediate Energy Region", Proc. Spec.

Meet, on Neutron Cross Section Standards for the Energy Region above 20 McV, Uppsala,

Sweden, 21-2:1 May, 1091, p.177-180 (1091).

19. llashiktira II,, Ihiikawa K., Tanaka S, and Kondo K.: "Calculation of Neutron Response of

Thermolumincscent Dosimeters", J. Faculty of Eng., Univ. of Tokyo, 39(1), 7 (1987).

20. Nakanc Y.: private communication.

21. Dickens J.K.: OKNL-6463, "SCINFUI/ A Monte Carlo Based Computer Program to

Determine a Seinlillalor Full lincrjjy Uesponsu to Neutron Detection for En Bclwccn 0.1 and

80 MeV: Program Development and Comparisons of Program Predictions with Experimental

Data" (1988).

22. "Data for Use in Protection Against External Radiation", Ann. ICRP, 17, 2f.\ (1987).

- 1 1 -

-JAMM-Diita/Coilo 90-005

T a b l e 1 DiniGi is io i i s of t h e i r o n s h i e l d a s s e m b l y a n d a d d i t i o n a l c o l l i t i m t o r ,and d e t e c t o r p o s i t i o n s .

Ep"(SleV)

43

67

Shieldthickness

(cm)

00

10102020404070

100

00

2020404070

100130

* I'roton energy.

Coltimalorlength(cm)

0800

700

600

4000

0800

600

40000

b Honncr ball counter.

' 7LiFand Z3JThand n " U F

I'euk flux ofsource neutron

(n/sr//iC)

3.15x10"3.45x10"3.15x10"3.45x10"3.15x10"3.45x10''3.15x10"3.45x10"3.15x10"3. J 5x10"

4.00x10"4.77x10"4.00x10"4.77x10"4.00x10"4.77x10"4.00x10"4.00x10"4.00x10"

fission counters.TLDs.

Detector posi(distance

IJC501A-

20,400

20,400

20,400

20,4000

_20.40

020,40

020,40

000

Hornier"-

0-0

• •

0

-0

0

0

tionfrom beum uxis)(cm)

V.C.c

0,20

0,20-

0,20-

0.20-

0,20

0,20-

0,20

0,20-

0.200,2020

TM>*-

-

--0-00

-...

-0-000

SSSTD*0

0

0

0

00

--0-0-000

Ren0

0

0

0

00

0-0-0-000

e Solid s t a t e nuclear track detector.The 15C5O1A, Hornier bal l , f ission and rem detectors were used for measurements behind theiron shields, and the TLD and SSNTD were used for measurements inside the iron shie lds ofmaximum thickness.

- 1 2 -

.JARRI- D/itn/Corio 1)0-000

Tub ID 2 Atomic compos)lions of the ironshield and the surrounding concrete.

Material Atom

Iron Iron

Concrete llydrojjcnOxygon.Sod i um

MagnesiumAluminumSilicon

I'otassiumCalcium

Iron

Atomic DensityC l o s e r 3 )

8.487

1.4984.1880.1230.0620.3121.1100.0380.4300.141

Table 3 Source neutron energy spectrum via the 7Li(p,n)reaction by 43-MeV protons.

Energy(MuV)

5.00EI00*

6. OOEtOO7.00EI008.00Ef009.00EI001.00EI0I1.10EI011.20IU011.30EI011.40Et011.50Ef01I.60EI0II.70EJ01l.80E(01l.90Et012-OOEtOl

2. lOEfOl2.20E1012.30E(012.40E10I2.50E101

' Read as

Flux(n/sr/MeV/jiC)

5.69E-024.72E-024.60E-024.38E-024.4IE-024.54E-024.48E-024.37E-024.68E-024.71E-025.34E-025.31E-024.63E-025.19E-024.94E-024.82E-024.83E-024.70E-024.76E-024.53E-024.20E-02

5.00x 10°.

Error

2.81E-032.46E-032.42E-032.39E-032.49E-032.36E-032.32E-032.11E-032.28E-032.85E-032.92E-032.81E-031.76E-031.82E-032.32E-032.19E-03

2.39E-032.31E-032.58E-032.15E-032.26E03

Energy(McV)

2.60E»012.70EI012.80EJ01

2.90EI013- 00EI013.10EI013.20E»013.30EMH3.40E»013. SOEtOl3.60Et0l3.70E+0I3.80E+013.90EI014.00EI014.10E101

4.20EI0I4.30E40L4.40EIOI4.50E4014.60EJ01

Flux(n/sr/JlcV/*C)

4.03E-024.29E-023.27E-023.58E-022.99E-022.64E-022.09E-022.10E-021.25E-021.24E-021.03E-026.19E-037.08E-03

1.28E-013.88E-013.88E-018.59E-023.74E-033.87E-047.53E-051.47E-04

1.2.1.1,1.1.i •

1.|,1,7.7.8.3.5.4.2.5.1.7.1.

Error

83E-0318E-0353E-0372E-0370E-0374E-0312E-0354E-0317E-0315E-0333E-0480E-0418E-044IE-038 IE-0373E-03

65E-0346E-0473E-0453E-0504E-04

- 1 3 -

.JAIWI-DMUI/CCHIU 00-00!)

Table \ Source neutron energy spectrum via the 7Li(p, n)reaction by G8-MeV protons.

Energy(McV)

5.00EI00*O-OOI'11007.00EK)08.00KIO09.00I': tool . O O E i O i1.10BI01l . 2 0 E * 0 lI.30E10!1 . 4 0 E » O II.50EIOIJ.flOEiOlI.70I-HOI1.80EI0II.OOEtOl2.00EMM2. lOEtOI2.20EKJI2.30Ef012.40EI012.50Ef012.80E1012.70EMH2. 80E»012. 90EV013.00EJ013. lOEfOi3. 20KI-0L3.30EI0I3.40E(0l3.5OEtOI3.60Ei013.70EKJI3.80EJ0I

Flux(n/sr/M/jiC)

1.14E-022.00B-0Z2.45E-022.43E-022.43E-022.56E-022.38E-022.20E-O22.85E-022.60E-023.08E 022.89E-022.78E-023.14E- 023.10E-023.33E-023.30E-023.34E-023.34E-023.79E-023.76E-023.70E-023.47E-023.74E-024.02E-023.83E-023.79E-023.82E-023.80E-023.85E-023.89E-023.73E-023.58E-023.68E-02

t

t

t

t

t

t

t

*

2.|,[,

1.2.1.1.1.1.1.2.1.1.1.

Error

74E-0350E-0353E-0355E-0355E-0359E-0352E-035IE-0373E-0363E-0378E-037IB-0369E-0384E-0391E-0397E-0398E-0393E-0377E-0301E-0394E-0395E-0389E-0392E-0309E-0374E-0377E-0379E-0375E-0393E-032IE-0375E-0388E-0378E-03

EnergyCM)

3.90EI014.00EI0I4. lOEfOI4.20EJ014.30EKH4.40Ef014.50EI0I4.60EI0I4.70E1014.80E+0I4.90EI01S.OOEfOl5.10EI015.20E10!5.30EI015.40EI0I5.50EI0I5.60EI0I5.70Ef015.80E1015.90Ef01B. OOEfOl6. lOEtOI6.20EI016.30EV016.40E+OI6.50E*016.60E+O16.70E+016.80K+016.90B+0I7.00EI017.10E+017.20E+01

Flux(n/sr/M/flC)

3.36E-023.48E-023.45E-023.44E-023.01E-023.29E-023.06E-023. ME-023.05E-023.07E-022.97E-022.7IE-022.97E-O22.56E-022.67E-022.30E-022.14E-022.05E-021.61E-021.22E-021.46E-027.50E-039.05E-037.72E-033.40E-022.28E-013.61E-012.59E-0I7.43E-029.98E-031.25E-036.29E-041.87E-049.09E-05

Error

. 9 IE-03

.4IE-03

.35E-03

.3IE-03-7IE-03.27E-03. 56E-03. 57E-03.18E-03. G3E-03

1.20E-03.50E-03.5GE-03.44E-03.46E-03

3.97E-041.29E-031.02E-031.01E-031.33E-031.44E-031.01E-03.09E-03

7.15E-042.04E-035.18E-036.41E-035. 32E-032.81E-031.01E-032.51E-042.35E-041.32E-049.09E-05

' Read as 5. OOx 10°.

- 1 4 -

JAKIil-Dntii/Codo 06-005

Table 5 Calculated neutron response function of the Uonncr ball counter.

Ivnerjjy Neutron responseboundary (counts • cm")

(cV)

tore' 1.5cm" 3.0cm 5.0cm 9.0cm4.00000Et08c0- 000001-:100 1.21200E-0I 6.62394E-0Z 2.46543E-01 7.14114E-013.50000EJ08 0.O0OO0EIO0 1.20400E-01 8.71040E-02 2.49249E-01 7.18018E-013.000001^08 O.OOOOOEfOO 1.18800E-01 7.32570E-02 2.73728E-01 7.00511E-012.50000EI08 0.00000IU00 1.13100E-01 7.8661715-02 2.93372E-01 8.43089E-012.00000EI08 O.OOOOOEIOO 1.1I000E-01 8.4838713-02 3.13194E-01 8.90955E-011.60000BI-08 0.000001'UOO 1.09000E-01 9.65422E-02 3.52922E-01 9.90692E-011.20000Ef08 O.OOOOOEtOO I.07200E-0I1.00000Bf08 0.00000IM00 1.07200E-018.00000Bf07 O.OOOOOEtOO 1.06900E-016.50000EI07 O.OOOOOEtOO 1.04900E-OI5.50000EI07 O.OOOOOEIOO 1.02400E-014.50000E*07 O.OOOOOEtOO L.01800E-01

10366E-01 3.99808E-01 1.10748Ef0022603E-01 4.42516E-01 1.2L633E+0034893E-01 4.86849E-0146848B-0I 5.29604E-0156024E-01 5.62324E-0I69035E-01 6.10579E-01

3. 50000EI07 3. 08890E-03 1. I8500E-01 1.99471E-01 7.19847E-01

33248EI0044291 El 0052658EIO065795Et0094066IMOO

2.75000EKI7 7.92810E-03 1.15400E-01 2.40935E-01 8.64964E-01 2.29764Ef002.25000IU07 1.13260E-02 1.28400E-0I 3.16469E-01 1.11515Et00 2.85595EIO01.75000Ef07 1.72980E-02 1.39600E-0I 4.2464415-01 1.43829E+00 3-48625EI00l.35000Ef07 2.31320E-02 1.26300E-01 5.34824E-01 L75848Et00 4.09864Ef001.00000Ef07 3.07170E-02 1.54100E-01 7.92599E-0I 2.49755EI00 5.32674EI006.70000Ef06 3.90230E-02 2.39900E-01 1.27319E+00 3.72H4E+00 6- 94474E+004.49000EI06 4.69170E-02 3.50900E-01 1.83004E+00 4.88226EI00 7.67178E1003- 01000B1-06 5.28540E-02 5.12600E-01 2.58673E+00 6.3l73lEiOO 8.51392K+002.02000EI06 5.47420E-02 7.28600E-0I 3- 48174K+00 7.72055E+00 8-76757E+001.35000EJ06 3.31540E-02 9.76200B-01 4.42043E+00 8.78493E+00 8- 18403K+009.07000EI05 1.55820E-02 1.38700EI00 5.53914Ef00 9.55978EI00 6.95255E+004.98000E105 1.83100E-02 2.O84O0EI00 6.80840Rf00 9.76846EI00 5.164991^002.24000Ef05 2.81430E-02 2. 92200Bf00 7.76509Et00 9.24283E+00 3.61335EI008.65000E+04 6.64210E-02 3.94900EV00 8.48133Ef00 8.39302E+00 2.57384EI001.50000EI04 1.61590E-01 5.17500BtOO 9.25074Et00 7.86099E+00 2.04393EfOO3.350001U03 4.01050E-01 6.596O0EKJ0 1.00090EI01 7.47934E+00 1.74043E+004.54000EI02 1.57150E+00 8.54800E+00 1.06606E+01 6-70883E+00 1.38113EHH)2.260001^01 4.53720Ef00 1.17100EI01 1.03980EI01 5.5363IEf00 1.03592Bf005.04000E*00 9. 59580Et00 1. 23900BI01 9. 08346E+00 4.43734EI00 8.04266E-011.12000Bf00 1.75920EMH 7.94100Ef00 6.99154Et00 3.25360B400 5.81233E-014. 14000E-01

' Response function of lie3 conuter (lOalm).b Thickness of moderator of the Bonner ball counter.c Read as 4.0000 x 108.

- 1 5 -

.1A GUI - PnUi/Criritj 90 - 005

Table 6 Fission cross sections of z;il!Th and z:i"U.

Knewboundury(cV)

4.0O00OEI083.75000E1083.50000EI083.25000Ef083.000001-^082.75000E1082.50000BI082.25000E1082.00000EI081.80000EI08I.60000Et081.40000Ef081.20000EI081. IOO00EfO8I. 00000EI089.00000Ef078. 00000Ef077.00000EI076.50000Ef076.00000Ef075- 50000Ef075.00000Ef074.50000Ef074.00000EI073.50000Ef073. OOOOOEf 072.75O0OEfO72.50000Ef072.25000EfO71.96000Ef071.75000Ef071.49000Ef071.35000Ef07

* Read as 4.Lower energy

*5.6.7.7.7.8.8.8.7.7.7.8.7.8.8.8.8.8.9.8.7.8.8.7.7.6.6.6.5.5.4.3.3.

Cross section(b)

'"Th

79I50E-01 1.63800E-0I 1.40800E-01 1.680I0E 01 1.83760B-01 1.00470E-0I 1.09I50E-01 1.I7960E-01 1.34890E-01 1.747I0E-01 1.53II0B-0I 1.04I00E-01 1.83140E-01 1.08390E-0I 1.42850E-0I 1.65330E-0I 1.73280E-01 1.98510E-01 1.04060E-01 I.72160E-01 1.91730E-01 1.29780E-01 1.34770E-01 1.84670E-01 1.56860E-01 1.54610E-01 1.46350E-01 1.48010E-01 1.80630E-01 1.08630E-01 1.42260E-01 1.71200E-01 1.19230E-01 1.

00000 x 108.boundary is 1.

30160EIOO3I280EI0032960EI0033940EJ0034340EI0033340EI0032540Et0032240EIOO32440EI0031940Ef0032270Ef0035160E10035830EI004!800Ef0044930EI0O48450Ef0052340Ef0053830EI0058930E)0063950Ef0064420Ef0066560Ef0068560EJ0067380EI0066210Ef0061730Et0058130Et0057170EI0047480Ef0021330Ef0023440E+001358OEtOO00340Ef00

OOOOOE-04

1.1.8.6.5.4.3.3.2.2.1.I.1.9.7.4.3.2.1.8.3.1.7.3.1.4.1.2.1.5.2.1.4.

Energyboundary(c-V)

22000EI0700000EI07I9000EI0670000EI0649000EI0649000EI0668000EI06OI0OOEI0646000EI0602000Et0665000EI0635000EI06HOOOEiOG07000Ef0543000EI0598000Ef0534000Et0524000EI0550000Ef0565000IM418000Ef0450000EI04IOOOOEfO335000Ef0358000Ef0354000Et0201000Et0226000Ef01O7OOOEfOl04000Ef0038000Ef0012000Et0014000E-01

(eV).

Cross

""Th

3.12670E-0I3.36980E-013.87460E-0II.99310E-011.49680E-01I.46240E-011.45990E-01I.27970E-0II.27I20E-011.03I50E-018.38I90E-02I.355I0E-021.78060E035. 96400E-041.19900E-04I.29510E-050. OOOOOEfOO0.00000EI000. OOOOOEfOOO.OOOOOEtOO0. OOOOOEfOO0. OOOOOEfOO0. OOOOOEfOO0. OOOOOEfOO0. OOOOOEfOO0. OOOOOEfOO0. OOOOOEfOO0. OOOOOEfOO0. OOOOOEfOO0. OOOOOEfOO0. OOOOOEfOO0. OOOOOEfOO0. OOOOOEfOO

section(b)

9.9.9.6.5.5.5.5.5.4.3.5.1.6.1.2.9.9.3.6.9.1.6.4.4.8.1.3.4.6.9.1.6.

8 *" U

78590E-0190390E-0175730E-0I56390E-0137I30B-0!61I80E-0I3383015-0138620E-0149190E-0195590E-01I4610B-O1I67I0E-0289980E-0252920E-0303340E-0357700E-0461590B-0590000E-0595290E-0512950E-0563850E-0510100E-0472000E-0600000E-0856240E-0871180E-0881650E-0709570E-0747160E-0746250E-0734230E-0743970E-0636560E-06

-16-

O B - 0 0 0

T a b l e 7 C a l c u l a t e d n e u t r o n r e s p o n s e s of 7 U P and B i l M F TLDs.

Energy Response a

(MoV) ("Cocq.R'cra8)1\A\- n a t U F

(MoV)Response

("Coeq.U-cm2)hncrjjy

(MoV)Response

"CR,\Y

543E-31H5-2I8E-167E-I5ZE-

1.64915(01'6.45015-1.45515(01 5.66215-1.28415+01 5.66215-1.13315+01 5.20415-1. OOOE+01 4.68815-8.82515(00 4.09915-7.788E+00 3.44215-6.87315(00 2.99015-6.06515(00 2.53015-5.35315(00 2.18615-4.72415(00 1.719E-4.16915(003. 67915+003.247E(002.86515(002.52815+002.23115(00 1.036E-

.969E+00 9.05715-

.73815+00 7.83615-

.533E(00 7.452E

.35315(00 6.543E-,19415(00 6.315E-.05415(00 5.453E-

9.30115-01 4.677E-8.209E-01 4.075E-7.24415-01 3.592E-6.39315-01 2.84415-5.642E-01 2.78215-4.97915-01 2.699E-4.39415-01 2.504E-3.877E-01 2.68215-3.422E-01 2.670E-3.020E-01 2.80415-2.665E-01 3.82115-2.35215-01 3.585E-2.07515-01 1.700E-

.83215-01 1.121E• 616E-01 9.773E.426E-01 8.753E.25915-01 6.86715.11115-01 6.706E

101010101010

-11

10 6.800E-10 5.988E-10 5.98815-10 5.533E-10 5.02815-10 4.437E-10 3.767E-10 3.290E-10 2.80415-10 2.43815-10 1.94915-

1.75115-1.50015-1. 387E-1.315E-1.296E-1.194E-1. 07915-9.669E-9. 239E-

11 8.192E-11 7. 871E-11 6.968E-

6.197E-5.634E-5.21615-

11 4.56215-4.65015-4.79715-4. 957E-5. 750E-6.879E-9.30915-l. 504152.090E1.76915. 14215

-12 7.79515-12 5.982E-12 4.940E-12 4.47415

-11 I.

10 9.804E-0210 8.65215-0210 7.63515-0210 6.73815-0210 5.94615-0210 5.946E-0210 5.24815-0210 4.63115-0210 4.08715-0210 3.60715-0210 3.18315-0210 2.80915-0210 2.47915 0210 2.187K-0210 1.931E-02

1.70415-021.50315-021.17115-029.119E-037.10215-035.531E-034.307E-033.35515-032.61315-032.035E-031.585E-031.23415-039.611E-047.485E-045-83015-044.540E-043.536E-042-754E-04

-10 2.145E-04-10 1.67015-04

1.30115-041.013E-047.889E-056.144E-054.785E-053.72715-05

101010

11111

-10-10-11

1.077E-9.631E-5.03915-3.43715-2.82015-2.80615-2. 80615-5.36IE-2.579E-2.13615-1.70915-1.787153. 03615-1.440E-1.14115-I. 00815-9.27415-8. 53715-6. 922E-5.44915-4. 63715-4.08015-3. 705E-3.48015-3. 377E-3.37915-3.47615-3. 66115-3.92715-4. 27415-4.71015-5.227E-5.83115-6.53215-7. 33615-8. 262E-9.317E-

. 05215-

. 18815-

. 34415-

.521 fi-

11 4.642E-12 4.41915-12 3.933E-12 3.80215-12 3.81315-12 3.917E-12 3.917E-12 4.30215-12 4.18215-12 4.31915-12 4.478E12 4.710E-12 5.080E-12 5.18815-

12 5.44715-•12 5.74215-•13 6.068E-•13 6.615E-13 7.420E-

•13 8.350E13 9.415E-13 1.063E-13 I.202E-13 1.36015-13 1.539E13 1.743E13 1.97415-13 2.236E-13 2.5331513 2.8711513 3.253E13 3.6861513 4.1771513 4.734E13 5.3651513 6. 08H513 6.8911512 7.810E12 8.8471512 1.002E12 1.136E

2.90215-2. 260151.76015 -1.37115-I. 068E-8.31515-6.47615-5.04415-3.928153. 059152.38215-1.855151.445151.125E8.764156. 826155.316154.140151.518E3.52415

05 1.72215-05 1.949E-05 2.20815-05 2.501E-05 2. 834E-06 3.211E-06 3. 63815-06 4.122E-06 4.67115-06 5.292E-00 5.99715-06 6.798E-06 7.70015-06 8. 72815-

-07 9.88715-07 1.12015-07 1.270E-

-07 1.438E--07 1.98715--10 3.4I7E-

12 1.287E-0912 1.45915-0912 1.653E-0912 1.87415-0912 2.12415-0912 2.407E-0912 2.727E-0912 3.090E-0912 3.50215-09

3. 96815-094.49715-09

12 5.09715-0912 5.774E-0912 6.54515-0912 7.414E-0911 8.40215-09

9.523E-091.07815-081.49015-082.56215-08

1212

11

11

10101010101010101010101010101010•10

•10

•09

09

* Road as 1.649 x 10 ' .

- 1 7 -

JAJOHI - UiiKi/Cuclif 00-005

Table 8 Cal cilia led neutron response of solidstate nuclear track detector (TS-1GN),

Energy(MeV)

1- O O K O l2 . 0 0 E 0 13.5015 014.35E-0I5. OOK-Ol6.00E-OI8.00E011. OOKfOO1.2215(00I.32EI00l.G5EiO02.00EIOO2.077EI02.35EIO02.81515102.944EI03.0015(003.21Ef00

Response(I ' i l s /n)

3.64315-044.91515-045.325E-046.58915-045 . 0 I 0 E 0 45.33915045.52IE-046.271B-046.015E-046.948E-047.587E-047.06915 048.29315-047.36815-048.92815 048.66415-047.96415-048.7C9E-04

Energy(MeV)

3.44EI003. 52151003.80EI004.0015(004.2715(005.OO15IOO6.OOE1OO6.29515(07.0015(007.74515(08.00E100LOOK'01L20EI011.5015)011.60151011.87515(12.0015101

Response(PilH/n)

9.508E 049.23915-049.15015-049.44615-049.517E-049.36415-049.54615-04I .017E039.42915-049.841I5-049.43915-048.85815 047.32715-042.84515- 042.41115042.21015-042.1611504

Read as 1.00 x 10-i

- 1 8 -

JAISKI-Dnlii/Coclo DG-000

Table 9 Measured neutron spectra behind Ocin thick iron bythe ВС5О1Л detector for 43-MeV |i-Li neutrons,

Energy Neutron l;lux Error Sou Iron l'lux Krror(cV) (п/сш*/1лЧЬагйу/дС) (%) (п/сшг/1л)1Нагву/йС) (fc)

!)() OOfi

Table 10 Measured neutron spectra behind 10cm thick Iron by theDCS01A detector for 43-McV p-Li iieutfobs,

(oV)h'tilttm FhnflVU/ (V)

bmtr V-otron Klux Error

4.4E/7'

' u E ' 74. IE»74. OH3.9E3.8E3.7E3.0E«73.5E»7

'77

7

3.4E3.3K3.ZK'73. IK-7SLOEZ.9E2.BK2.7E2.6E2.5EZ.4B2..IK2.2E2. IK2. onI.9EI.8EI.7EI.6EI.5E1.4K«7I.3E-7I.2E-7I. IB»7i.or.»7

7. OF.-66.GE-65. OF.-6

beam axis4.G05E-3I.252E*2.758EtI. I93E'4. II4F.»2.5I3E'9- 753F.?3.2G7F/32.097E-32.275E-32.6I3E»32.95IE»3

3.661E-33.770E«33.945E-34.190E-34.41 BE • 34.47GE-34.303EM

3.660E-33.36BE«33.087E-32.8I6E-32.6I6E'32.524E-3

2.28IF.»3993C3

.725E'3

.537EM

.346E-3J I 8 E ' 3

9.082Ef2

7!640E*25 . ! ' '

I. I05E IG.4I3E-22.633E-22.473E23.720E24. I I5E2% 81 IE 2I. I59E II.6G7E 1I.O57E I7.19IE 28.780E 2LQ7GE ILOOSE IG. 812E t3.930E 21.375E28.587E21.379EI.G5IE1.589EI.254E7.648E2.067E

I23EI.532EI.789E I9.8I8E 24.1 WE-29.S53E-23.369E-29.565E-2.665E• 6I7K-30IE-.146E-

6.252E-I.5IJE-

20 eta (tm2.306E-17.559E* II.02OE'22.93 IE? 2

HI.903E-I.7I4E-L 388F.'1978E'5.030E'4.8I7E'5.272E'0 7 0G. I05E*6.430K'G. 653K-6.755E*6.730E*6.6-I8E*6.5G9K'6.494E*6.395E*6.274E*6.I7IE'GJI7K'6.08 IE'5.974E-5.73 IF.-5.I22K-S.22IE'5.256E'5.420E*5.469Ek

5.355E'S.277E-5.392E-5. G26E*5.496E-

3.087f:I.0I2E7.276E7.5IGE5.145KI.068EI.46IE IL8I8E I9.38ZE 21.38!!: II.592E II.274E II.08GE (B.7I9E-Z5 5 5 f i 23< \ffl, 23.509E27.I58E-2I.2I9E-II.49GE-II.397E II.O4IE I6-025E2L770E-24.6I2E 29.268E 2I.039E-I5.968E 22.G89E 25.5I6E-2L837E-24.01 IF. 28.I75E-25.39IF.23.686E-22.680E 2I.066E 2I.260E I2.825E-I

10 cm (urn2.035E?O6.808E»01.373EfI.8S0K*I.809E?I.5I5E'I.I72K-7.727F.'O4.999E'OI.45GK-05.002K'05.7O4E'OG.258KfOO.583EtO6.70^06«77OE'O6.952F/07.3O4E'O7.68GE»07.89DE»07.8G2E'O7.B30F/07.285E-06.854E*0G. 3161/05.8C7E-05.625F.-05.7I2F.-05.895F.'OS.828EfO5.494E-05.223E'O5.222E«05.4O5E'O5.652E-05.974E-0G.G29F.-07.374E-0

ax (H2.287E-1L203E I9.192E-21.026E-18.3B4E-21.I54E-I2.34IE-13.222E IL 30GE II.693E II. GIGE IL237E IL040K-I8.58 IF.5.688K3,388K3. G75E6.95 IE-2.II0K I.3131: I.2I8E I

9.225E 25.476E 2

779E-2743E 2

.0I3E

. I60E-G.255K2.675E5.273E-.91 IE

4.444E 26.865E-5.678E-3.675F.2.585F.I.003E9.782EI.B9ZE-I

4.4 x 10' .

20

Table 11

JAKUI--titdn/Cuik Dfl~(

Measured neutron spectra behind 20cm thick Iron by theBC501A detector for 43-MeV p-Li neutrons.

Energy(eV)

4 4Fi7'4.3E(74.2Ef74. IEt7'. OE * 73.9Et73.8Et/3.7E>73.0Ef73.5Et73.4E(73.3Et73.2KI73. Wtf3.0Ef72.9Ef72.8Et72.7Et72.GEf72.5Ef72.4Et72.3EI72.2E»72. IE»72.0E»7l . 9 E f 7I.8F.»7I.7E»7I .6E»7I.5E>7l . 4 E r 7l . 3 E t 7I . 2 E » 7t . I E > 7I.OEf7O.OE'G8. OK'G7.0E»66.0E'65.0EtG

' Read

Neutron Flux(n/cro2/Lethargy/JIC)

bean axis1. ItSEfS3.220EI37.499EO1. I27EMI.OO7Et45.0I2ML430EI3G.438Ef27.633EI28.40IEf28.753D2&917Ef20.0G3EI29.148E*29.240E»29.410E»29.734Ef2I.0I4EI3I.O44Et31.048Ef3I .01ID39.449E»28.609Ef 27.70BEf28.860E»26.l89Et25.765E»25.5O5F.f25. !92Er24.663E»23.969Ef 23.283Ef22.7OIF>t22.2I3E*2l.797Et2l.520Et21.508K^2l.496Ef29.150Etl

as 4.4 x 10'.

Error(%)

I 658B-2.303E-I.842B-9.973E-S5.362B-53.320E-8- 7G2E3.978E-3.453E-3. GO IE2.045E-I.789E-I.240B-0.808E-1

8 . 7 8 1 E '9.GG0E '1.255E-I.047E-1.986E-2.15IE-2.077E-1.740E-1.104E-2.723E-'1.025E1.9I8E-2.005B-1.198E-3.438E-4.778E-

Neutron Flux Error(n/cmVi-t'thurny/ziC) (%)

20 cm from2.7G3EH7.307EHl . 5 l9Et2

! 2.250EJ2I 2.416Et2

2.052B»2L487EJ29.034EH5.I27EM3.940EH4.079EH4.41 OEM4.027EH

I

Ii

i

i

t

.713KM

.707EU

.002EM

.630EH

.G3GEH

. 6 6 I E H

.642EH\. 527E* 14.3I8EH4.064E* 1

I 3.828EH3.625EU3.440EH3.298EH3.I92EH

2 3.II2EM2 3.040EH

2.643E-2 2.987EMI.493E-2.7I2E-3.230E-3.148E-I.788E-2.753E-5.629E-2.32GE

1 2.964EH1 2.932EH1 2.847EM1 2.753EH

2-750EM1 2.87IEf|1 2.900EHi 2.27tF.fi

jcarn axiif8.420E-55.7I9E-J3.9I5E-53. 977E-S3.737E-S4.084E-S1.17IE1.604E-6.232E-JI.2I5E-I.243E-I.027E-9.334E-J7.984E '5.360E!3.205E!3.G03E-!7.289E-:I.223E-I.49IE-1.409E-i. 085E-6.538E-!1.918E!5.537E'1.149E-I . 3 I0E7.268E-'3.150E-6.70 IE2.169E-5.175E8.I28E-7.158E-4.987E3-698E'

Neutron KJux Error(n/cmVl-etharKy/iiC) (%)

40 cm from 1! 2.3GGIMI 5.772EI0I I.I70BH! I.650EH! i. 680EI1! I.366EH

8.94GEfO5.399EK)

I 4. IGlEfO4. IO8EfO4.204Ef 04. l95EfO

I 4.I35F.I0I 4.I18F.I0I 4 . 1 7 3 E I OI 4.240P.I0I 4.23CErOI 4. l22EfO

4. OOlEfO3.974EM)4.034EJ0

1 4.093E»02 4.103Ef02 4. lOGEtO2 4.170EH)1 4.264E»0

4.231E>02 3.9411^02 3.507EK)2 3.222E(02 3.235Ef 02 3.406E»02 3.495Ef 02 3.423EJ02 3.324EtOI 3.378KrO

I.44IE-2 3.45IE>01. G57E3.437E-

2.96OEfO1 i.755EfO

Kttta ax if*2.393B-12.5I7IM2.9I3E-1I.589E-1I.349E-12.020E-13.234E-I5.833E-II.973E-I2.060E-12.202E-1I.8I5E-1I.599E-II.337E 18.847E-25.539E-26.615E-2I.275E-I2.126E-I2.562E-I2.32IE-1I.687E19.766E-23.137E-2G.9G9E 2I.389E-II.570B-9.845E-24.175E-29.230E-23.323E-26.509E-29.960E-28.615E-25.927E-24.384E-2I.769E-22.362E-G.5I9E-

_ o j —

,IAKHI-Dfil(i/Co(Jo 5)0-005

Tablo 12 Muasurcd neutron spectra behind 40cm thick Iron bythe UC501A detector for 43-MuV p-Ll neutrons,

Energy(eV.) (n/

4.4EI7*4.3Et74.2Ef74.1E»74.0E»73.91^73.8Ef7Qt { \'j i I

a6E»73.5EI73.4Ef73.3Ef73.2E»73. l E f 73.0E»72.91'>72.8EJ72.7Et72.6E»72.5Ef72 .4E»72. mi2.2Et72.IE (72.0Et71.9Et7l . 8 E f 71.7Et7I . 6 E f 71.5Ef7I .4E H1.3Ef7l.2Ef7i. miI .OEf79.0Et68.0E>67.0EI66.0Et6S.0E>6

* Read as

Neutron FluxumVUstharijy/jiC)

beam axis8.705EH

. 9 4 2 E I 23.922EI25.260EI24.59IEI22.54IEI28.99IEH2.836EU2.073EI)2.562EH3. I05EH3.532EU3.842EH4.055EH4. 183EM4.234f)t I4. 217EH4. 157EH4.080EHi . O O l E f l3.912EU3.807EU3.685EU3.559EH3.418EU3.227EH2.941EH2.568EU2.183EHI.882EHI.699EH1.587EH1.465EH1.284EH1.069Efl8.595EfO6.529EK)5.532EfO6.227BfO

4.4 x 10r.

Error( fl' *i\ A)/

1.254E 15.757E-22.583E-23.384E-J5.254!') J6.305E-J4.738E-J1.806B-I2.514E-I1.586E-1.048E-8.737E-J8.1781) J7.499E-S6.859E-J7.2IIB-J9.123E-SI.240E-1.569E-1. 7431)1. 662E-I- 329E-7.872E-J1.773E-56.328E-J1.11IE-1.166E-7.266E-J2.187E-J3.8O2E-51. 928E-J9.710E-J1.569E-I.753E-1.668E-9.798E-J2-016E-5. 356E-3.653E-

Neulron FluxCn/cffl?/LotharKy/(

20 cm from6.384EI0.805EI

3.9811')!G. 085Kf

' 8.408Ef.998EI

' 3.292EI. 996IU,254Ei.0I7EI.013EI.052EI

! l.082Ef! I.093EII I.085E)] 1.0641':*! I.039EI

I.OI5Et9.899E»09.555E)09.052EI08.405E»0

! 7.7I7EI0I 7. !02E»0! 6.583EtO

6.141E(U5.820E(0

I 5.646EI0I 5.491EI0I 5.228EK)I 4.944EJ0I 4.742EI0

4.485EfO4.084EI03.8l7EfO

I 3.884EfO4.218EK)4.562EfO3.857E»0

Error0 (i)

beam axisI.584EI.003E-0.571E -i6.403E-J6.005K-J7. 36IE-S2.248E-3.088E-1. I09E2.006E-2. 092E-I.732E-I.558E-I.328E9.03IE-55.566E-J6.295E-SI.266E-2. 185!*:2.752E2.684E--2. I20E-1.302E-4. 05IE-51.160E-2.45 IE2.830E-I.577E-7. I44E-!1.489E-5. 069E-J1.235E-2.023E-1.900E-1.371E-9.972E-J3-760E '4.007E-1.700E-

Noutron I'l ux Error(n/cmVLetharKy/iC) (X)

40 cm from I9.880E2.025EI0

' 3.880Ef0S.927EI0

! C529EI0! 4.882EI0

2.641E10

j

II

.568EtO

. 4 6 7 E I 0

. 5 4 9 E I 0

.559E»0

. 5 I Z E I 0,440E»0. 3 6 I E t O. 2 9 4 E I 0.243EtO.206EtO. I 7 4 E I 0. 145I-:iO. 1 I 8 E I 0. 093E4 0.063EI0. 0 1 9 E t 0

I 9.532E-8.708E-7.861E-7.220E-6. 938E-

l 6.9I7E-l 6.907E-I 6.8091)1 6.726E-1 6.706B-1 6.622E-1 6.439E-1 6.454E-l 6.952E-1 7.319E-1 5.873E-

jcam axis2. II3E 1I . 2 I 5 E II . 0 0 3 E I1.076E 16.686E-21.205E12. 996E-14. 851 E lI.479EI1.407E-II.506E-II . 3 2 9 E II.2C9E-I1.145E-I8.122E 25.10IE-25.848E 21. I86E-I2.043E-I2.540E 12.400E-I1.8I3E-1I.076E 13.452E-29.456E-22.072E 12.4811) I1.423E-16.31IE-21.2IIE-14.06 IE -29.3B8E-2I.457E-11.262E-18.748E-26.466E-22.487E-22.690E-15.452E 1

- 2 2 -

ЛЛ1'Ж1-П/Нп/С<л1и ПО — 005

ТнЫе 13 Measured neutron spectrum Table 14 Measured neutron spectrumbehind 70cm thick iron by behind 100cm thick iron bythe 11С501Л detector for the ИС501Л detector for43-McV p-Li neutrons. 43-MeV p-Li neutrons.

Unorijy Neutron Flux Кггог Клогку Neutron Flux Hrror(oV) (п/сш'/ичйагку/лС) (JO (oV) Сп/сша/Ьс1Магиу/лС> (W

i. ' . . i_ _ »

Table 15 Measured neutron spectra beliind Ocm thick iron bythe ВС501Л detector for 08-M<;V |>-U nmilrons.

КпсгкУ Neutron Flux Krror Neutron I'lux Error(eVj (n/cfflVl.utharKy/iiC) (.%) (п/Ы'/ичЫщу/Ю (%)

.JAMUI-bntn/Codo 06-005

Table 16 Measured neutron spectra behind 20cm thick Iron bythe ВС001Л detector for G8-MeV п-Ll neutrons.

Кпсгку Neutron Flux Error Neutron Flux Error Neutron Flux Error(cV) (n/cm7l.cthaw/<iC) (*) (n/cmVI-etharKy/йС) (*) (n/craVLclharKy//(C) (X)

.JAKKI-lJnUt/Codo 0(1 — 005

Table 17 Measured neutron spectra behind 40cm thick iron bythe BC501A detector for 68-McV p-l-i neutrons.

taorjjyCoV) (n/

7.0EI7'6.8EJ76.6Ef 76.4Ef76.2EI76.01^75. mi5. mi5* 2EI75.0Etf4. 8EP74. 6Ef74.4EJ74.3Ef7

i \i\i4. mi3.9Ef71 Q 1*1-7

3. 7Ef73.6IU73. 5IU73.4E+73.3Ef73.2Et73. lEf73. 0Ef72.9Ef72.8Ef72.7IU72. 6E»72. 5Ef72.4EI79 QI-H7

2. 2EI72. Hvt-72. OEf 7

.9Ef7l.8Ef71.7Ef7I.6E1-71.5Ef7l.4Ef7I. 3E*7l.2Ef71 lEt7- 0 E I 7

9.0Ef68. 0E*67. 0E*66. OE+6

' Read as

Neutron FluxctfiVlx'(.fiarf{y//;C;

beam axis

1.317Ef33.2I3EI32. 691 El3I.O69Ef32.624Et21.533EI22.234EI22.779EI23.067EI23.230EI23.2I9EI22.959EI22. 696EI22.547EI22.429Et22.323E122.2I3EJ22. HIEf22.047EI22.042EI22.078E+22. lO3Ef22.063Ef 21.947E121.792Ef21.663E+21.607Et21.621Et21.651E*21.628E+21.518EI21.348Et21.192E4-21.108K+21.081EJ2I 030Ef28.995EH7.298EH6- 101K+15.7UEH5.636EH5.490EH5- 364E+15.355EH5.443EH5.643EH5.988Et 16.519EH6.986E+16.517EH

7.0 x 107.

Error) (X)

8.026E-24.89GE-26.730E-2I.496E-3.008E-2.934E-I.640E-7.589E-J5.6I1E-J5.957E-J6. 985E-J7.435E-J8.049E-J8.380E-S8.62IE-J9.483E--J1.093E-1.230E-I.290E-I.222E-I.060E-9.006E-J8.405E -J9.132E-51. I08E-1. 257E-1. 126E-8. 569E-J8. 153E-S1. 042E-1.455E-1. 890E-2.001E-1. 674E-1. 154E-6.590E-;1. 288E-2.472E-3.224E-2.555E-1.638E-1.708E-8. 348E-J1.338E-1.593E-1.302E-9.3I0E-!5. 990E-!4.127E-'2.338E-

Nculron FluxCn/ait2/Iclhamy/f

20 cm from2.495EH.420EI2

2.908IU22.426EI2

.739E127.527EI13.027EI3.824E)

! 4.967EI! 5.700EI! 6.067E)I 6.1G2EI! 5.953EI! 5.C39EII 5.425EI-! 5.262Et! 5. IGOEl

5.104EI5.060E)4.997EI4.891 E(4.731EI-

! 4.523E(I 4.29IE>I 4.057EI

3.826EI3.597Ef3.381 El

I 3.208E*I 3.096Ef

3.007EI2.874EI2. 670EJ2.430E12.212EI2.043E*

I

!

III

.914Et

. 807E»

.713EH

.833E»

.565Et

.488Ef|

. 398Et

. 3 3 1 E t

.309Etl

.300EH

.276Et1

.293EM

.401 EH• 577EH

ErroriV (%) (r

beam axis1.384 E l8.502E-25. 873E-28.487E-2I.207K-I1.318E1I.922E-II.222B-I5.404I-: 24. 065E- 24.340K-25.0491: 25.218E-20. 293B- 25.268E-25.272E- 25. 795K- 26.838E-27.322E-27-605E--27.381E 26.785E-26. 177E-26.052E-26. 670E-27. 906E-28. 688E-27.835E-26.250E-26. 363E-28.623E-21.207E-11.499E-1I.526E-1I.279E-19.109K--24.989E-29.28IE-2I.55M: I1.794IM1.373E-19.483E-21.098E15.679E-29.228E-21.102E-19.514E-27. I93E-24.449E 22.966E-2

Neutron Flux/cmVl-olbnrKy//^

40 cm from 13.943EI08.470EI0I.838EH2.103EH9.624EI04.867EI05.586EI0G.09!Et0G.463EI06.775EI0G.971EfO7.000EI0G.8G6EI00.70IEIO6.579EI06.456EJ0G. 339EI0G.228EI0G.I 23E10G.020EJ05.911EI05.790EI05.650EI05.493EI05.32GEI05. I58EI04.995EI04.836EK)4.67IE104.487E104.280EI04.055EI03.826EI03.604i:i03. 396EfO3 1961'̂ 02J96EI02.793EtO2.601Ef02.446EK)2.355EI02.332EfO2. 350Ef02.367EI02.359E»02.330E(02.307Et02.332EI02.448EfO2.665E*0

Error:) (%)

joiim a x i sI.3IIE-12.GI3E-II.GI2E 1I.403E-I3.540E-13.450E-1I.I78E-II. I30E-I7.303E-25. IGflE-24.600E-24.433E--24. 107E-24.013E-24.183E-24.5861-:-25.193B-25.944E-28.539E-26.907E-27.050E-27. 022E-26.908E 26.760E-26.590E-26. 378E-26.144E-25.990E-2G. 067E-26.468E-27.147E-27.889E 28.327E-28. 074E-26.932E-25. 047E-22. 963E-24.869E-26.940E-27. 629E-26.599E-24.618E-23.108E-23.058E-24.148E-25.099E-25.180E-24.010E 21.5611: 22. 846E- 2

- 2 6 -

00-005

Table 18 Measured neutron spectrumbehind 70cm thick iron bythe UC501A detector for68-McV p-Li neutrons,

Table 19 Measured neutron spectrumbehind 100cm thick iron bythe DC501A detector for68-MoV p-Li neutrons.

Energy(eV) (n /

6.8IU7*6.6EI76.412176.212176-0Ef75.8EI75.6EI75.4EI75.2Ef75.0EI74.8EI74 .6EI74.4(217

4 212174. l E f 74.012(73. 9Kf73.8KI73.7Ef73.6EI73. 5E1-73.4Ef73.3EI73.2EI73.1E f 73.0E*72.9EI72.8EI72. 712(70 C I? i 7Z. Ob i /

2.5IU72.4Ef72.3EI72.212(72. lEf72.012171.912(71.8Ef71.7Ef71.6Ef7l.5E*7i mi1.312(71. 2F.I71. IE ft1.0Ef79.0Ef68.0Ef67.0Et66.0Et6

* Read as

Neutron Fluxc[nVLeUiartfy///C;

beam axis3.004EH7.445EH6.989EH4.354EU1.313EU2.172EI04.401EI06.014EI08.521EI09.587EfO0.459EI07. 932EI06.724EI06.325EI06. 244EI06. 282EfO6. 22712(06.001EI05. 69512(05.45312(05. 329EK)5.24512(05- 064Eh04.734E fO4.36312(04. !66EtO4.306Et04.717EI05.089EI05.05512+04.481EI03.61812(02.912EI02.650EI02.748EtO2.878EtO2.784EI02.482E(02.175EfO2.008EI01.965E(0l.975E(01. 978EfO1.942EK)1.929EI01.987EtO2.077EI02. 17612(02.145E(01.66812(0

6 .8 x 107 .

Error) (X)

1.26712-6.93IE-28.917E-21.287E-I2.118E-I7.261E-12.918E-1I .05IIH6. 888E-26. 895E-28.135E-29.450E-21.09812-1.156E-1.162E-1.219E-1.348E-1.503E-I.615E-1.597E-1.440E-1.244E-1.145E-1.214E-1.450E-1.612E-1.375E-9.828E-!8.72 IE-!1.046E-1.454E-2.026E-2.325E-1.976E-1.312E-7.512E-I1.281E-2.177E-2.715E-2. 299E-1.574E-1.432E-7. 331E-1.114E-1. 278E-1.069E-

Enerj;yCeV)

6.8EI7*6.6Ef 76.4EI76.2Ef76.0Ef75. BE 175. BE 175. 4Eh75.2EI75.0Et74.8EI74.6EI74.4EI74.3EI74.2EI-74. !Ef74.0EI73.9EI73.8Ef73.7E173.6EI73.5ES73.4Ef73. 3Ef73 2Ef73. 1EI73.0Et7

i 2. mii 2. mi

2.7K+72.6Ef7

I 2.5Et72.4EI72.3Et72.2Ef7

I 2.1EI71 2.0EI7

1.9Et71 !. 8Ef71 I.7EJ71 1.6Et71 \MMI 1.4EI71 1.3EJ71 1.2EI71 1.1 E»7

8.093E-2 I. QEf76.135E-2 9. OE-fG1.076E-1.927E-

8.0E167.0Ef66.0EJ6

* Read

Neutron Flux(n/cni'VLcthurKy/y/C)

beam ax i s8.067E-12.274EI02.575EI01.569E104.566E-

.357E-2.2I1E-3.154E-3.732E-3.992E-3.7G0E-2.999E-2.416E-2.200E2.139E-2.178E-2.243E-2.280E-2.267E-2.207E-2. 11612-2. 009E-.884E-.731E-.559E-.432E-.439E-.598E-.794E-.855E-.702E-.423E-. 190E-.097E-. 107E-

|. 124E-. 092E-.017E-

9.315E-28. 674E-28- 479E-2B.782E-29. 208E-29. 242E-29. 00IE 29.085E-29.638E-2

.014E-19.507E-26- 833E-2

as 6-8 x 107.

Error(«

1.76512-7.792E-21.08812-I.845E-3.145E-5.962E-2. 882E-1. IO7I2-7.93IE-28.47912-21.047E-1.295E-11.555E-11.G50IMI.680E-11.773E-1I.930E-12.076E-12-151E-12.105E-11.936E-11.71412-11.57112-11.626E-11.947E-12.235E-1I.962E-II.408E-11.202E-11.305E-11.646E-12.16212-12.376E-12.002E-11.433E-9.706E-21.53912-2.409E-12.87512-12.54612-11.82012-11.426E-17. 77912-21.044E-11. 123E-19.82H2-27.779E-25.621E-21.058E-12.138E-1

- 2 7 -

JAIH'il-DnUi/Coiiu 06 -005

Table 20 Measured neutron spectrumbehind 130cra thick iron bythe BC501A detector for68-MeV p-Li neutrons.

[•In orgy(eV)

6.8IU76. OEf 76.4EI76.2IU76.0EI75.8EI75< 61*f 75 .4EI75 .2E t75. OEf 74.8EI74. 6Ef74 .4Ef74.3EI74.2IU74. lEh74.0Ef73.9IU73.8Ef73.7EI73.6Ef73.5EH73.4Ef 73.3P.V73.2Ef 73. lEf-73. OEf 72.9Ef 72.8EI-72. 7E+72. 6Ef-72.5EV72.4EI72. 3Ef72.2Et72.1E+72. 0EI71. 9E+71.8Ef71.7EI71.6Bf71.5E+71.4EI71.3Ef71.2Ef71. lEf71.0Ef79.0Ef68. OEf 67. OEf 66- OEf 6

* Road

Neutron Flux(n/cmz/LotharKy//iC)

boam axis5.212E-21.167E-17.148E-26.278E-22.871E-25.186E-37.440E-3I.033E-21.160E-21.232E-21. 377E-21.623E-2I.745E-21. 728E-21.626E-21.465E-21.289E-21.150E-21.076E-21.051E-2I.033E-29.920E-39.407E-39.112E-39. 078E-38. 974E-38.525E-37.876E-37.378E-37.075E-36.642E-35.890E-35.098E-34.689E-34.656E-34.568E-34.193E-33.917E-34.230E-34.901E-35.218E-34.952E-34. 395E-33.901E-33.829E-34.140E-34.481E-34.933E-35.620E-36.255E-3

as 6.8 x 107.

Error(X)

3.342E-1I.963E-14.194E-14.492E-14.852E-1I.554EK)8. 80IE-13.5I0E-12.460E-I2.627E-I2.752E-12.276E-I2.079E-12.089E-12.254E-12.655E-13.303E-13.997E-14.388E-14.285E-13.834E-I3.310E-12.903E-12.718E-12.855E-13.082E-12.967E-12.633E-12.605E-12.735E-13.035E-I3.616B-13.786E-13.225E-I2.521E-12. I35E-13.308E-14.835E-I4.894E-13.862E-12.81 IE-]1.991E-11.440E-11.938E-11.803E-11.524E-1I.288E-17. 580E-27.463E-21.121E-

- 2 8 -

JAHrit-Dnln/Codo 06-005

Table 21 Measured reaction rates behind iron by theBonncr ball counter for 43-McV p-Li neutrons.

Counter

licire

1.5cm3.0cm5. Ocm9.0cm

Reaction rate(n//iC)

20 cm thick1.08170Ef03*7.70767EI032.13367EfO42. 27974EI041.78810EI04

Reaction rate(n/sO

40 cm thick2.32029EK)23.09448Bt037.54156EI039.20984BKJ34.56463BI03

Reaction rate(n//iC)

100 cm thick2.29024EI-011. 85478Ef023.94076BKJ24.7I565BKI21. 59787Bf02

* Read as 1.08170 x 103.

Table 22 Measured reaction rates behind iron by theBonner ball counter for 68-MeV p-Li neutrons.

Counter

Bare1.5cm3.0cm5.0cm9.0cm

Reaction rate(n/jiC)

20 cm thick9.20495EI02*1.08745Ef043.31695E+045.13089EI043. 84652Ef04

Reaction rate<n/*O

40 cm thick4. 94764Ef027.58654EI031. 85827EI042.24907BI041.34443EI04

Reaction rate(n/nC)

100 cm thick7.23828EKH6. 28653EI021.30211EI031. 34292K+035.40227EI02

* Read as 9.20495 x 102.

- 2 9 -

•JAKHI —Data/Code Ofi-005

Tal/le 23 Measured neut ron s p e c t r a behind i ron by the iJonner ha l l counterfor 43-MGV f J -L i neu t rons .

f'lnoruy(cV) (

4.500EI07*3.500EJ072.750EI072.250Ef 071.750EI071.350EI071.00OEt076.700EI064.490EI063.010EI062.020EI06l.350E*069.070EJ054.980EI052.240Er058.650EI04l.500Et043.350EI034.54 OE 1022.260Er015.040EI001.120EI004. HOE 01l.OOOE-04

Neutron Fluxn/cmVLctliartfy/iiC)

20cm thick2.740E1036.395EI025.945EI024.454EI023.016EI022.027Et02!.245EfO2I.3I6EI021.753EI022.725EI023.424EI024.830Et027. 1I1EI028.604EI024.851EfO22.700F>024.618E»OI2.620Ef0l2.930Ei011.769EJ018.083E4-005.673Ef 003.083Er00

Neutron Flux(n/c(n7Lotharny//(C)

40cm thick9.760EI012.277EI012.677EI011.203EI011.088EI016.209E1004.294EI005.434EI00I.629EI012.354E10I5. I5IEI018. 128IU011.965EI023.787EI022.0731') 102l.570Et021.798EI011.238Ef013.361E»003.892Ef001.233Ef 001.036Ef 006.747E-0I

Neutron FluxCn/cmVU'lharKy//iC)

100cm thick8.940E-025.349E-021.415E-025.843E-035.I41E-031.069E-027.898E-031.549E-027.986E-026.793E-02I.369E-012.440E-013. 249EI001. l47Ef019.915K+001.200IM11.015Ef008.151E-011.190Et006.792E-014.982E-022.216E-013.199E-02

Read as 4.500 x 10'.

- 3 0 -

JABRI-Ddln/Codo 06-C

Table 24 Measured neutron spectra behind iron by the Dormer balfor 68-MeV p-Li neutrons.

counter

Energy(eV)

8.000E+07*6.500Ef075.500EI074.500EI073. 500E+072.750Ef 072. 250IU071. 750Ef071. 350Ef071.000Et076.700EI064.490EI063.0l0Ef062.020Ei061.350EKJ69. 070Ef054. 980Ef052.240Et058. 650E4041.500EI043- 350Et034.540EKJ22.260E.015. 040EtOO1.12OEt0O4.140E-011. 000E-04

Neutron Flux(n/wnVLcthaf«y//iC)

20cm thick1.190E+036.935EI032.458EI031.866EtO31.345EI038.752EI025.086EI024. 332EJ022.940EI022.68 3E1023.227BfO25.317EtO27.730Et02

1.032Et031.47LBfO31.937EK131.776EI03T. 556EI022.506EJ023.540K+0I2. 018Ef0I1.072EJ014. 297EI003.210EI003. 045EI003.437EtOO

Neutron Flux(n/cmVl-otharjjy/jiC)

40cm thick1.752BKJ29.746EfO22. 874EI022. 185EI02I.310E+021.05IEf024.134IJf015.888EUH3.836Ef014.429EI014.553E40I6.325B+011.312BfO21.754EI023.185E+026. 238Ef029.477E1025.293BW22. 938EfO24.733EI013.383Ef011.424EI015.617E1-003.107Ef002. lgiEfOO1.201Ef00

Neutron Flux(n/cmVUthaa'y/iiC)

100cm thick

5.770E+001.593EKM3.469EI004. 852EfOO2.727EtOO4.563Et001.570B-I008.451E-012.4131-^006.809E-014.022E-017.252E-011.394E+001.894EKJ02. 629Ef009. 968E+003. 244E+012.462Ef014.171K+0I5.577EI004.850E+002.132E1001.515EI004. 835E-012.606E-011. 855B-01

Read as 8.000 x 107.

- 3 1 -

JAKKI-Data/Corfu 00-OOfi

Table 25 Measured fission reaction rates ofand m T h for 43-MeV p-Li neutrons.

Cos i t ion7/

(an)

0102040700

10204070

Rb

(an)

00000

2020202020

* Thichnuss" Distancec Read as 8

Fission reaction2,1 ft

(n/itO

8. 01E*4"2.43EM5.64Ef32.97EI26.06E»0I. 0OBt22.47EI21.95E125.I4EI13.0IEI0

U(%)

(0. 59)(1.00)(1.81)(3.43)(9.76)(4. 30)(5.74)(3. 53)(5.02)(19.6)

of iron shields.from the beam axis..01 x \0\

rale

(n/iiC)

3.27E+4I.02BI42.49Ef31. 16EI2I.79E+0

6. I2EH1.77EHL53EI0

Th(

(0.(0.(0.(3.(27

(17(14(20

%)

24)89)99)34).7)

.4)

.0)

.9)

Table 26 Measured fission reaction rates of 2;iHUand 2S*Th for 68-MeV p-Li neutrons.

Position7/

(cm)

020IJ70

100204070

100130

R*(cm)

00000

2020202020

(

1.1.1.3.2.7.1.1.2.1.

Fission reaction2 1 8

18Et5c

53E+423E+318EH59E+014EH68EI258EU57E+008E+0

1)\ /O/

(0. 38)(0.66)(2.26)(7.14)(11.0)(3. 96)(3.41)(5.95)(9.25)(11.9)

rate2 3 2

<n/*C)

5- 71E+47. 70Ef35.47EI-21.08Efl8.51E-14.69E+I1.15Ef27. l2EtO9.07E-14.59E-1

Th

(0. 49)(0. 90)(3.28)(11.9)(18.6)(4. 73)(4.01)(8.61)(15.1)(17.7)

' Thichness of iron shields.b Distance from the beam axis.c Head as 1.18 x 10 \

- 3 2 -

JAKlil-lMii/CucIo 00-005

Table 27 Difference of neutron reaction rates ofrLiP and n"LiF TLDs for 43- and 68-MeVp-Li neutrons.

Position*(cm)

4070

100130

' Thichncssu Read as 2.

Difference("Coeq.R/fC)

43 MeV2.60E-7"1.58B-73.50E-7

of iron shields.60 x 10"7.

of rouction(X) (

63.12.8.

228

rateMCoeq.R/j©

08 MeVI.07E-63.68E-71.30E-72.86E-7

40.210.315.112.1

Table 28 Measured neutron reaction rates using solidstate nuclear track detector for 43- and 68-McV p-Li neutrons.

Position1

(cm)

010204070

100130

* Thichness0 Read as 3.

(1

of99

' i ts/cm2

433.99EMI.83EH6. 23EK)9.21E-11.16E-12.00E-2

Reaction/(C) (X)

MeVb 5.6

6.25.57.98.1

16.0

iron shields.x 10 ' .

rate(Pits/cm 7 JiC)

68 MeV

I.64EH3.29EtO5.19E-18.63E-Z8.35E-3

(X)

5.45.56.18.9

24.1

- 3 3 -

J A K M - D I I I M / C V N I U (1(9 — fKJft

TuUIc 29 Measured neutron reaction rates using a rcmcounter made by Fuji Co. Ltd, for 43- and68-McV p-Li neutrons,

I'iml tlon"(cm)

010204070too

* Thiehnoss* K«id an 4.

Huuctlon mto(»Sv/jC) (%)

43 VuV4.23i:t0h(0.50)1.62M) (0.32)7.4 IK 1 (0.35)1.98K-1 (0.38)3.33E-2 (0.31)7.07K 3 (0.32)

of iron shields.23 x IOU.

Position(cm)

0204070100130

Keuction rule(jSv//iC) (\)

68 JfuV4.581: »0 (0.45)l.52KtO (0.28)4.60E-1 (0.41)9.06E-2 (0.62)I.93E-2 (0.76)4.061: 3 (0.45)

Table 30 Measured neutron reaction rates using the DC50IAand (tanner ball detector for 43- and 68-McV p-Lineutrons.

I'osilion' Reaction rate Position Reaction rule(cm) (I.SV/IC) (cut) («.Sv/«C)

2040100

43 M1.30I.60E-I'3.25F.3

2040100

G8 He3.095.29E1. GOF,

V

12

• Thichncss of iron shields.* feud us 1.60 x 10 '.

3t

(a) TOP VIEW

\ shielding wall (concrete)

experimentalassembly

7Li target 232Th-FC

P + ^ " | rZjdearingNmagnet

en

filler (iron ball and iron sand)

units in cm

Fig. 1 Cross sectional view of the TIARA facility withthe experimental arrangement.

(b) SIDE VIEWadditional

iron collimatoriron

shield

Fig.2 Top view and side view of experimentalarrangement for the iron shield withadditional iron collimator.

.JAKUI-lMu/Cudu Ofi-005

BC501A PM BASEDynode

PA DLA

Anode

HV

SCA

DA

CFDR1IC

sealer

gale.LO ADC1

gatey=r. LO ADC2

Istart

TAC ». i» L0 ADC3

RF trigger •- CFDJstop

Flg.3 Block diagram of the electronic circuits. PA:pre-amplifier, DLA: delay lineamplifier, SCA: timing single channel analyzer, DA: delay amplifier, RIIC:risc-tiine-to-pulse-height converter, CFD: constant fraction discriminator,TAC: tliae-lo-amplitude converter, LO:linear gate stretcher, ADC; analog-to-digital converter. The sealer was used for counting the number of realevents from the detector in order to estimate the counting Joss.

2xlOJ

u

1.5xlO

lxlOJ

5xlO8Cou

1 i • i ' r • \lr:- 68MeV p - Li

43MeV p-7Li

,- I..'0 10 20 30 40 50 60

Neutron Energy [MeV]70 80

Fig.4 Source neutron spectra generated via the 7Li(p,n)reaction by 43- and 68-MeVprotons. The spectra were measured by the time-of flight methods with theBC501A scintillation counter and absolutely normalized by the measurementsusing the recoil-proton counter telescope.

- 3 6 -

JAIWI-PiiUi/Codu Ofi-(

10'

,o«

llO"1

ao

,-2

I 1 I I I '

Neutron response of Bonner Bull detector

I., S N

bare1.5cm thick3.0cm thick5.0cm thick9.0cm thcik

i . . 1

10" 102 10'1 10'1

Neutron Hncrgy (cV)10"

Fig.5 Neutron responses of the Bonner ball counter for each moderator thickness:bare, 1.5, 3.0, and 9.0 cm. The almost responses were calculated by Uwaminoet al. from adjoint calculations using the ANISN code except for the detectorwith 1,5-cm thick moderator. The response for the detector with 1.5-cm thickmoderator was estimated by Ishikawa et al.

U

10Neutron Energy (cV)

10° 10'

Fig.6 Fission cross sections of 2 3 HU and 2:i2Th. The cross sections up to 20 MeV istaken from JENDL-3, the cross sections between 20 and 400 MeV have beenmeasured by Lisowski et al.. and above 400 MeV have been calculated by himusing the HETC code.

- 3 7 -

Ofi-OOfi

10*

ej j j j 1 p

Responses of 7LiF and niltLiF TLDs

. I . . i . . i . . i . I . . i .io~(l io"5 io"r io"J i o r \orl~ i

Neutron Energy (MeV)

Fig. 7 Calculated neutron responses of 7l,iH and n " L i F TLDs usinga code developed by llasliikura e l a l .

10

c

s

•g

coa-

10

Neutron response of solid state nuclear track detector

TS-16N

,-4

10rl 10"Neutron Energy (McV)

10'

Fig.8 Calculated neutron responses of solid state nuclear trackdetector (TS-16N) using the SSNRES code.

- 3 8 -

10*

105

1 0 -

10"

43MeV p-Li neutrons on Iron

100cm (hick

107 2Neutron Energy (eV)

Fig.9 Measured neutron spectra by the BC501A detectorbehind various thickness of iron on the beamaxis for 43-MeV p-Li neutrons.

io-

10'

J2I

10"

43MeV p-Li neutrons on 0cm thick Iron

107 ^Neutron Energy (eV)

Fig. 10 Measured neutron spectra by the BCsOlA detectorbehind 0-cm thick iron at the positions of 20 and40 cm from the beam axis for 43-MeV p-Li neutrons.

T

cc

10"

43MeV p-Li neutrons on 10cm thick Iron

40cm from beam axis (xO.l)

107 I 5Neutron Energy (cV)

Fig.11 Measured neutron spectra by the BC501A detectorbehind 10-cm thick iron on the beam axis and at thepositions of 20 and 40 cm from the beam axis for43-MeV p-Li neutrons.

to1

=0

to-'

IO1

10°

43MeV p-Li neutrons on 20cm thick Ironr

U-^H

io7 =Neutron Energy (eV)

Fig. 12 Measured neutron spectra by the BC5QU detectorbehind 20-cm thick iron on the beam axis and atthe positions of 20 and 40 cm from the beam axtsfor 43-MeV p-Li neutrons.

r

10J

43MeV p-Li neutrons on 40cm thick Iron

10s

oNeutron Energy (eV)

Fig. 13 Measured neutron spectra by the BC501A detectorbehind 40-cm thick iron on the beam axis and atthe positions of 20 and 40 cm from the beam axisfor 43-MeV p-Li neutrons.

10'

10'

6SMeV p-Li neutrons on Iron

-t**H*F '40cm thick

130cm thick

107

Neutron Energy (eV)

occ:

I

Fig. 14 Measured neutron spectra by the BC501A detectorbehind various thickness of iron on the beam axisfor 68-MeV p-Lx neutrons.

toI

100

a

3

X

c

s1

6SMeV p-Li neutrons on 0cm thick Iron

20cm from beam axis

107

10s

Neutron Energy (eV)

Fig. 15 Measured neutron spectra by the BC501A detectorbehind 0-cm thick iron at the positions of 20 and40 cm from the beam axis for 68-MeV p-Li neutrons.

io4

68MeV p-Li neutrons on 20an thick Iron

10'

20cm from beam axis

40cm from beam axis

Io

Neutron Energy (eV)

Fig. 16 Measured neutron spectra by the BC501A detectorbehind 20-cm thick iron on the beam axis and atthe positions of 20 and 40 cm from the beam axisfor 68-MeV p-Li neutrons.

CMI

104

u

iou

6SMcV p-Li neutrons on 40cm thick. Iron

107

40cm from beam axis

Neutron Energy (eV)

Fig. 17 Measured neutron spectra by the BC501A detectorbehind 40-cm thick iron on the beam axis and atthe positions of 20 and 40 cm from the beam axisfor 68-MeV p-Li neutrons.

io5

104

10u

3

10"

10"

43MeV p-Li neutrons on Iran

20cm thick (xlOO)

100cm thick

• J I -' -I •J J • •

10"' 10° 10l 1O1 103 104 10s 10* 10T

Neutron Energy (eV)

CO

I

Fig. 18 Measured neutron spectra by the Bonner ball counterbehind various thickness of iron on the beam axisfor 43-MeV p-Li neutrons.

10e

10s

104

10'

"I 1 1 1 1 1 T"""I

68MeV p-Li neutrons on Iron

...j .....J ,..,,,110"' 10° 10l 102 103 10"1

I I

Vf 10°Neutron Energy (eV)

10'

Fig. 19 Measured neutron spectra by the Bonner ball counterbehind various thickness of iron on the beam axisfor 68-MeV p-Li neutrons.

b

fact

ion

105

104

103

102

101

10°

in-1

—i—i—

r

: \

i N

- /

-

i i

- r - i—|

Fission

43MeV

- o -

\

\

• i i

—i r— i i i i

Reaction Rates

p-Li

? Ui > s U

\

neutrons on

beam axis20cm frombeam axis20cm from

x

• • *-Iron :

beam axis

beam axis •

-.

-

-.

} ' *

0 50 100Shield Thickness (cm)

150

Fig.20 Measured fission reaction rates of 2 3 8U and 232Thbehind iron on the beam axis and at the position of20 cm from the beam axis for 43-MeV p-Li neutrons.

noC3

I

en

L

13a

105

10*

3

102

101

10°

n"1

t Fission Reaction Rates

V\ 68MeV p-Li neutrons on\ \ —o— 2X2Th beam axis

\ \ —A— -fh 20cm from*3\ -«•--- TJ beam axis

\ \ ...A— u 20cm from

- \

- %

V, , i , i . . i , i

-

Iron

beam axis

beam axis

-

-

_

1 r t

50 100Shield Thickness (cm)

150

Fig.21 Measured fission reaction rates of 2 3 8U and 232Thbehind iron on the beam axis and at the position of20 cm from the beam axis for 68-MeV p-Li neutrons.

(J

I

Rat

e (P

iR

eact

ion

101

10°

10"1

io-2

\

\\ \

43

t %

. . . . . .

Reaction Rate of

V*

\ \

\ \

\ \ 68 MeV

\ \MeV \ \

\

\ \

\

> • ! • • > •

| i . t .

SSNTD

-

-

•

\

\

0

Ta

oocc

CO

I

50 100Shield Thickness (cm)

150

Fig.22 Measured reaction rates of solid state nucleartrack detector in the iron shield on the beamaxis for 43-and 68-MeV p-Li neutrons.

enI

u

10-1

oQ

s2"3CJ

Z10,-2

10-3

Neutron dose equivalent

43 and 68MeV p-Li neutrons on Iron

Fuji rem counter 43MeVFuji rem counter 6SMeVBC+Bonner 43MeVBC+Bonner 68MeV

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Fig. 23 Measured neutron does equivalent by the rem countermade by Fuji Co. Ltd. for 43-and 68-MeV p-Li neutrons.In this figure the measured neutron does equivalentby the BC501A and Bonner ball detectors are also shown.

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