INTERNATIONAL NUCLEAR DATA COMMITTEE. 232 EXTENSION OF THE Th BURNUP CHAIN IN THE WIMSD/4 PROGRAM LIBRARY
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1 ISS! IN DC International Atomic Energy Agency INDC(BZL)-034 Distr.: L INTERNATIONAL NUCLEAR DATA COMMITTEE 232 EXTENSION OF THE Th BURNUP CHAIN IN THE WIMSD/4 PROGRAM LIBRARY Alexandre D. Caldeira Institute of Advanced Studies (Aerospace Technical Centre, Department of Research and Development, Ministry of Aeronautics, Brazil) Translated by the IAEA October 1991 IAEA NUCLEAR DATA SECTION, WAGRAMERSTRASSE 5. A-1400 VIENNA
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3 232 EXTENSION OF THE Th BURNUP CHAIN IN THE WIMSD/4 PROGRAM LIBRARY Alexandre D. Caldeira Institute of Advanced Studies (Aerospace Technical Centre, Department of Research and Development, Ministry of Aeronautics, Brazil) Translated by the IAEA October 1991
4 Reproduced by the IAEA in Austria October
5 EXTENSION OF THE 232 Th BURNUP CHAIN IN THE WIMSD/4 PROGRAM LIBRARY Alexandre D. Caldeira Institute of Advanced Studies (Aerospace Technical Centre, Department of Research and Development, Ministry of Aeronautics, Brazil) 1. INTRODUCTION 232 In the WIMSD/4 program library [1] the Th burnup chain ends 234 at U. The purpose of the present work is to extend this chain to U by modifying the U burnup data in the program library Th BURNUP CHAIN 232 The burnup chains for Th and U available in the WIMSD/4 program library are shown in Fig. 1 by solid lines, while the broken line 234 indicates the change made in the U burnup data. The modifications needed in these data are given in Appendix A 3. RESULTS In order to analyse the influence of this modification on the behaviour of k. f and U number density as a function of time, we processed the TRX1 [3] problem with the LEOPARD [2] and WIMSD/4 programs, replacing U of the fuel by Th. It was necessary to make an adjustment in the initial number density of U, which was done by processing several times with the WIMSD/4 program in order to make the k. value of the system slightly supercritical. Figures 2 and 3 show graphs of k. f and U number density, respectively. These graphs show the results obtained with the WIMSD/4 program, using the old and new libraries, and with LEOPARD. Appendix B gives the input data used for the processing of the LEOPARD and WIMSD/4 programs. 4. FINAL COMMENTS Although this modification needs a thorough analysis, Figs 1 and 2 show an improvement in the values obtained with the WIMSD/4 program and the new library in comparison with those derived from the LEOPARD program. production of U by radiative capture of U should be considered in 232 the Th burnup chain. Thus, the This improvement shows that the WIMSD/4 program library needs to be revised with a view to updating and inclusion of important materials like Np and U so that the burnup chains can be considered fully. 3
6 Th-232 n, Y Pa-233 U-233 n, Y ^ > U-234 n, Y U- n,y U-236 Fifi Th burnup chain. I. OS UIM3 ( BIB. MOVfl ) UIH5 ( BIB. ÍNTICA 1, LEBPRR3 i i i i i i i i i i i i i i i i i i i i i i i i i i i i i i i i i i i i i i i i i i _ * TEMPS ( OlflS 1 S.00 / 10' i I i i i i i i i i i Fie. 2. k. as a function of time. [Abscissa axis: time (days) ] a inf WIMS (new library) WIMS (old library). LEOPARD
7 3.00 UIM3 I BIB. NOVfl ) U1M3 I BIB. RNTICfl I., LEOPARD i i i i i i i i i i i i i i i i i i I i i i i i i i i i ~ 9. OC i. 00 i. t i i..i, t - L i i > i ' TEMPS ( DIBS ) 0.60 / 10' o.so 1.00 FiR- 3. U number density as a function of time. [Abscissa axis: time (days); ordinate axis; U number density ] WIMS (new library) WIMS (old library). LEOPARD 5. ACKNOWLEDGEMENTS The author thanks L. Henrique Claro for the results generated by the LEOPARD program and for important discussions on the WIMSD/4 program. 5
8 REFERENCES ] ROTH, M.J., MacDOUGALL, J.D., KEMSHELL, P.B., "The Preparation of Input Data for WIMS", AEEW-R538, Atomic Energy Establishment, Winfrith, Dorchester, Dorset, England (1967). ] BARRY, R.F., "LEOPARD - A Spectrum Dependent Non-Spatial Depletion Code for the IBM-7094", USAEC Report WCAP (1963). ] "Cross Section Evaluation Working Group Benchmark Specifications", BNL 19302, ENDF-202, Brookhaven National Laboratory, Upton, N.Y., USA (1974). APPENDIX A , U burnup data in the old library U burnup data in the new library E E+01.OOOOOOOOE+OO OOOOOOOOE+OO
9 APPENDIX B B.1. Input data for the LEOPARD program * * * * * * CÉLULA TRX-1 + THORIO (TESTE) CTA/IEAV * * * * * * E E E E E
10 B.2. Input data for the WIMSD/4 program CELL 6 SEQUENCE 2 NGROUP 18 2 NMESH 8 NREGION 4 NMAT 3 1 NREACT 2 PREOUT INITIATE * TRX1 BENCHMARK MATERIAL E E-02 MATERIAL E-02 MATERIAL o" E E-02 ANNULUS ANNULUS ANNULUS ANNULUS REGULAR 1 FEWGROUPS MESH POWERC BEGINC SIGPUNCH BUCKLING.0057 NOBUCKLING LEAKAGE 5 THERMAL 4 DIFFUSION BEEONE -1 DNB 1 DNB 2 DNB E E-02 REACTION PARTITION PRINTC BEGINC 8
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