Author:
Ahmad Siraj-ul-Islam,Ahmad Nasir,Aslam
Subject
Nuclear Energy and Engineering
Reference27 articles.
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. Neutronic calculation to the TRIGA Ipr-R1 reactor using the WIMSD4 and CITATION;Dalle;Ann. Nucl. Energy,2002
4. Effect of neutron cross section evaluations on neutron spectrum determination;Griffin;IEEE Trans. Nucl. Sci.,1992
5. Halsall, M.J., 1980. A summary of WIMS-D4 input options AEEW-M 1327, Winfrith
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