Reactor physics calculations and their experimental validation for conversion and upgrading of a typical swimming pool type research reactor

Annals of Nuclear Energy

Volumn 27, Issue 10, 2000, Pages 873-885

  Ali Khan, Liaquat ^a   Ahmad, Nasir ^b   Zafar, M S ^c   Ahmad, Ayaz ^a  

^a PAKISTAN ATOMIC ENERGY COMMISSION   (Pakistan)

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

^c UNIVERSITY OF THE PUNJAB   (Pakistan)

Author keywords

[No Author keywords available]

Indexed keywords

COMPUTER AIDED ANALYSIS; COMPUTER SOFTWARE; NEUTRONS; NUCLEAR FUELS; REACTIVITY (NUCLEAR); REACTOR SHUTDOWNS; RESEARCH REACTORS; SAMARIUM; URANIUM; XENON;

NEUTRON FLUX; SOFTWARE PACKAGE CITATION; SOFTWARE PACKAGE WIMS;

REACTOR CORES;

EID: 0033900664     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0306-4549(99)00097-3     Document Type: Article

References (7)

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2. Aslam K.L.A., Ahmad N. Core neutronics of research reactors using low enriched uranium in MTR type fuel. Turkish J. of Nuclear Sciences. 24:1997;67-76.
3. Fowler, T.B., Vondy, D.R., Cunningham, G.W., 1971. Nuclear reactor core analysis code CITATION. ORNL-TM-2496 Rev. 2.
4. Halsall, M. J., 1980. Summary of WIMS-114 input options. AEEW-M 1327.
5. Research Reactor Core Conversion Guide-Book, Vol.3, Analytical Verification. 1992;International Atomic Energy Agency, Vienna.
6. 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, Revision-1. Technical Report, Pakistan Institute of Nuclear Science and Technology, PO Nilore, Islamabad, Pakistan.
7. Liaquat, A., Ansari, S.A., Shami, Q.D., Iqbal, M., 1994. Neutron Flux Measurements in the Full Power LEU Core of PARR-1. Technical Report No. PINSTECH-138, Pakistan Institute of Nuclear Science and Technology, PO Nilore, Islamabad, Pakistan.