Neutronic and thermal hydraulic analysis for production of fission molybdenum-99 at Pakistan Research Reactor-1

Annals of Nuclear Energy

Volumn 35, Issue 2, 2008, Pages 345-352

  Mushtaq, A ^a   Iqbal, Massod ^a   Bokhari, Ishtiaq Hussain ^a   Mahmood, Tariq ^a   Mahmood, Tayyab ^a   Ahmad, Zahoor ^a   Zaman, Qamar ^a  

^a PAKISTAN INSTITUTE OF NUCLEAR SCIENCE AND TECHNOLOGY   (Pakistan)

Author keywords

[No Author keywords available]

Indexed keywords

IRRADIATION; MOLYBDENUM; NEUTRONS; NUCLEAR REACTORS; THERMAL EFFECTS; URANIUM;

FISSION MOLYBDENUM; NEUTRONICS; THERMAL HYDRAULIC ANALYSIS;

FISSION PRODUCTS;

EID: 37849021284     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2007.06.006     Document Type: Article

References (10)

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2. Bokhari I.H., Israr M., and Pervez S. Analysis of reactivity induced accidents at Pakistan Research Reactor-1. Annals of Nuclear Energy 29 (2002) 2225-2234
3. 99Mo production. In: International Meeting on reduced Enrichment for Research and Test Reactors, October 3-8, 1999, Budapest, Hungary.
4. Deen, J.R., Woodruff, W.L., Costescu, C.I., 1995. WIMS/D4 User Manual REV.0, ANL/RERTR/TM-23.
5. Fowler, T.B., Vondy, D.R., Cunningham, G.W., 1971. Nuclear Reactor Core Analyses Code CITATION, ORNL - TM - 2496 Rev. 2.
6. Halsall, M.J., 1980. A Summary of WIMSD4 Input Options, AEEW-M 1327.
7. IAEA-TECDOC-1065, 1999. Production technologies for molybdenum-99 and technetium-99m, International Atomic Energy Agency Vienna.
8. 99Mo production. International Atomic Energy Agency Vienna.
9. Pakistan Research Reactor-1, September 1992, Final Safety Analysis Report (FSAR) for Conversion to LEU Fuel and Power Upgradation. Revision 1.
10. Rubio, R.O., 1993. INVAP SE "BORGRS v3.0".