Effect of new cross-section evaluations on criticality and neutron energy spectrum of a typical material test research reactor

Annals of Nuclear Energy

Volumn 31, Issue 16, 2004, Pages 1867-1881

  Ahmad, Siraj ul Islam ^a   Ahmad, Nasir ^a   Aslam, ^a  

^a PAKISTAN INSTITUTE OF ENGINEERING AND APPLIED SCIENCES   (Pakistan)

Author keywords

[No Author keywords available]

Indexed keywords

FLUX SPECTRUM; NEUTRON ENERGY SPECTRUM; NEUTRON FLUX; THERMAL FLUXES;

BENCHMARKING; DIGITAL LIBRARIES; HEAT FLUX; HYDROGEN; MATERIALS TESTING; NEUTRON SCATTERING; PROBLEM SOLVING; SPECTRUM ANALYSIS; THERMOANALYSIS; WATER;

RESEARCH REACTORS;

EID: 4444250263     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2004.06.005     Document Type: Article

References (27)

1. Aslam, Ahmad N., 2002. Effect of coolant channel width on group constants and multiplication factor of research reactors using MTR type low enriched uranium fuel. Ann. Nucl. Energy 29, 477-488.
2. BNL, 1990. ENDF-102 data formats and procedures for the evaluated nuclear data file ENDF-6, BNL-NCS-44945-01/04 (last revised 2001).
3. Dalle, H.M., Pereira, C., Souza, R.G.P., 2002. Neutronic calculation to the TRIGA Ipr-R1 reactor using the WIMSD4 and CITATION. Ann. Nucl. Energy 29, 901-912.
4. Griffin, P.J., Kelly, J.G., Luera, T.F., 1992. Effect of neutron cross section evaluations on neutron spectrum determination. IEEE Trans. Nucl. Sci. 39 (6), 2078-2085.
5. Halsall, M.J., 1980. A summary of WIMS-D4 input options AEEW-M 1327, Winfrith.
6. IAEA, 1993. The evaluated nuclear data library of NEA Data Bank (JEF-2), IAEA-NDS-120, Rev.2.
7. IAEA, 1997. Chinese evaluated neutron data library (CENDL-2), IAEA-NDS-61, Rev. 4.
8. Khan, L.A., Ahmad, N., Zafar, M.S., Ahmad, A., 2000. Reactor physics calculations and their experimental validation for conversion and upgrading of a typical swimming pool type research reactor. Ann. Nucl. Energy 27, 873-885.
9. Khan, L.A., Israr, M., Arshad, M., Karim, A., Akhtar, K.M., Moquit, A., 1992. Pakistan Research Reactor-1: final safety analysis report for conversion to LEU fuel and power upgradation, Nuclear Engineering Division, Pakistan Institute of Nuclear Science and Technology, Islamabad.
10. Leszczynski, F., 2002. Description of WIMS library update project (WLUP). In: International Meeting on Reduced Enrichment for Research and Test Reactors, Bariloche, Argentina, November 3-8.
11. Leszczynski, F., Aldama, D.L., Trkov, A., 2003. WIMS-D library update, Final report of a co-ordinated research project.
12. Malkawi, S.R., Ahmad, N., 2000. Prediction and measurement of neutron energy spectrum in a material test research reactor. Ann. Nucl. Energy 27, 311-327.
13. Malkawi, S.R., Ahmad, N., 2001. Solution of the neutron spectrum adjustment problem in a typical MTR research reactor. Ann. Nucl. Energy 28, 25-51.
14. Manokhin, V.N., 1989. BROND USSR evaluated nuclear data library, IAEA-NDS-90, Rev. 2.
15. Matzke, M., 1994. Unfolding of pulse height spectra, The HEPRO Program System, Report PTB-N-19, Physikalisch-Technische Bundesanstalt, Braunschweig.
16. McElory, W.N., Berg, S., Crockett, T., Hawkins, R.G., 1967. A computer automated iteration method for neutron flux spectra determination, Report AFWL-TR-67-41, vol. I-IV, Air Force Weapons Laboratory, New Mexico.
17. Nakagawa, T, Shibata, K., Chiba, S., 1995. Japanese evaluated nuclear data library Version 3 Rev.-2, JENDL-3.2, J. Nucl. Sci. Technol. 32, 1259.
18. Okumura, K., Mori, T., 2003. Integral test of JENDL-3.3 for thermal reactors. In: Proceedings of the 2002 Symposium on Nuclear Data, Tokai, Japan, November 21-22, JERI-Conf 2003-006, pp. 15-21.
19. Perry, F.G., 1977. Least square dosimetry unfolding: the program STAY'SL, Report ORNL/TM-6062, ENDF-254, ORNL.
20. Pervez, S., Iqbal, M., 1998. Performance evaluation of converted and upgraded PARR-1. Presented at the 1998 International Meeting on Reduced Enrichment for Research and Test Reactors, October 18-23, Sao Paulo, Brazil.
21. Roth, M.J., Macdougall, J.D., Kemshell, P.B., 1967. The preparation of input data for WIMS, AEEW-R538.
22. Saleem, M., Parvez, A., Arshad, M., 1995. Calculation of lattice cell constants for the IAEA PHWR benckmark using the computer code WIMS-D4. Nucleus 32 (1,2), 1-11.
23. Thiyagarajan, T.K., Ganesan, S., Jagannathan, V., Karthikeyan, R., 2002. A computer program with graphical user interface to plot the multigroup cross sections of WIMSD library. Ann. Nucl. Energy 29, 1735-1745.
24. Trkov, A., 2004. Personal correspondence with Dr. Andrej Trkov.
25. WLUP, 2001. The updated WIMS-D libraries derived from the basic evaluated data files. Available from: 〈http://www-rcp.ijs.si/_wlup〉. Related documents are also available here.
26. Zijp, W.L., Zsolnay, E.M., Nolthenius, H.J., Szondi, E.J., 1988. Final report on the REAL-84 Exercise, Report ECN-212.
27. Zuniga, A., Ravnik, M., Cuya, R., 2001. Application of reactivity method to MTR fuel burnup measurement. In: International Conference on Nuclear Energy in Central Europe, September 10-13.