Moderator temperature effect on reactivity in light water moderated experimental reactors

Annals of Nuclear Energy

Volumn 27, Issue 11, 2000, Pages 969-983

  Mohapatra, D K ^a   Mohanakrishnan, P ^a  

^a INDIRA GANDHI CENTRE FOR ATOMIC RESEARCH   (India)

Author keywords

[No Author keywords available]

Indexed keywords

COMPUTER SOFTWARE; EXPERIMENTAL REACTORS; MODERATORS; NUCLEAR FUELS; REACTIVITY (NUCLEAR); TEMPERATURE MEASUREMENT; THERMAL EFFECTS; URANIUM;

LIGHT WATER MODERATED REACTORS; SOFTWARE PACKAGE COMESH; SOFTWARE PACKAGE SMAXY;

LIGHT WATER REACTORS;

EID: 0033749808     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0306-4549(99)00104-8     Document Type: Article

References (18)

1. Ekberg, K., 1994. CASMO-4 expansion of KRITZ experimental data. Studsvik Core Analysis 1994-01-13.
2. Halsall, M.J., Taubman, C.J., 1986. The 1986 version of WIMS nuclear data library, AEEW-R2133.
3. Huria H.C. Evaluation of the lattice physics code 'MURLI' for light water systems. Annals of Nuclear Energy. 8:1981;183-198.
4. Jagannathan V.et al. A fast and reliable calculation model for BWR fuel assembly burn up analyses. Annals of Nuclear Energy. 7:1980;641.
5. Jagannathan, V. et al., 1987. COMESH - a corner mesh finite difference code to solve multigroup diffusion equations in multidimensions. BARC-1367.
6. Johansson, E., 1989. Comparison of calculated and measured reactivity coefficients for light water reactor lattices. Proceedings of an Advisory Group Meeting Organized by IAEA, IAEA-TECDOC-491.
7. 2O/fuel pin lattices at temperatures up to 245°C. Studsvik Report, STUDSVIK/NS-90/133.
8. Johansson, E., Edenius, M., 1983. Benchmarking of a CASMO/CPM 69- group library based on ENDF/B-5. Proceedings of Thermal Reactor Benchmark Calculation Techniques and Results, BNL-EPRI-NP-2855.
9. Kim, J.D., 1990. WIMKAL-88, The 1988 version of WIMS-KAERI library. IAEA NDS-92.
10. 2 cores with soluble poisons. Journal of Nuclear Science and Technology. 29(12):1992;1201-1211.
11. Mohanakrishnan, P., 1990. LWR assembly code SMAXY and its IGCAR version. IGCAR report, RPD/CPOS/21.
12. Mohanakrishnan, P., Lee, S.M., 1998. PWR lattice benchmark solutions. Presented at the 1998 International Conference on Physics of Nuclear Science and Technology, New York.
13. Radkowsky A. Seed Blanket Reactors in CRC Handbook of Nuclear Reactors Calculations, Vol-III. 1986;CRC Press, Florida, USA.
14. Rose, P.F., 1991. ENDF-201 ENDF/B summary documentation (ENDF/B-VI) BNL-NCS-17541.
15. Shiroya S.et al. Experimental study on temperature coefficient of reactivity in light-water moderated and heavy-water- reflected cylindrical core loaded with highly enriched uranium or medium enriched uranium fuel. Journal of Nuclear Science and Technology. 32(11):1995;1081-1089.
16. Sathyabama N., Mohanakrishnan P. Evaluation of reactivity worth of air filled beam tubes in a small neutron source reactor by 3-D transport calculations. Journal of Nuclear Science and Technology. 29(12):1992;1133-1142.
17. Taubman, C.J., 1975. The WIMS nuclear data library, AEEW-M 1324.
18. Yamane T.et al. Measurement of overall temperature coefficient of reactivity of VHTRC-1 core by pulsed neutron method. Journal of Nuclear Science and Technology. 27(2):1990;122-132.