Optimizing the Neutronic Parameters for VVER-1200 Reactor Core Using WIMS-ANLS Code
https://doi.org/10.26583/GNS-2018-01-09
EDN: XQXHDV
Abstract
In this paper, the WIMS-ANL is used to obtain different keff values and maximum keff values by varying the size of the cooling sink of the fuel assembly of the reactor (VVER-1200) and the fuel UO2 concentration (1 to 30%).
References
1. J.G Tyror & R. I. Vanghan. An introduction to Neutron kinetics of nuclear power reactor. Second edition: point reactor kinetics. 2011, p. 182. (in English)
2. W.L. Woodruff, Argonne National Laboratory, USA and L. S. Leo Pando: “Upgrades to the WIMS-ANL Code and Library. Philippine Nuclear Research Institute, Sao Paulo, Brazil, 1998. (in English)
3. Yoshiaki Oka, Katsuo Suzuki (edited). Nuclear reactor kinematics and plant control. Second edition. Tokyo, Japan, Springer, 2008, pp. 501–519. (in English)
4. D.M. Titova, et al. Approaches to optimization of the core reactivity coefficient for the ‘master’ heat supply reactor. Obinisky institute of nuclear power engineering, national research university (MEPHI), Russia, 2015. (in English)
5. Bengt pershagen. Light water reactor safety. Substantially revised and updated edition: Studsvik AB, Nykoping. Springer, 1988, pp. 466. (in English)
6. Teresa Kulikowska. Reactor lattice transport calculation. Institute of atomic energy, Swierk, Poland, 2000, pp. 19–21. (in English)
7. Carl Bergl., et. On measuring and monitoring of reactivity in subcritical reactor systems with Monte Carlo neutronics. KTH School of engineering, Department of physics, Sweden, 2014, pp. 15. (in English)
8. Dan Gabrial Cancuci. Handbook of nuclear engineering. Vol. 1: Nuclear engineering fundamentals. Springer, 2010, pp 1172. (in English)
9. Amir Hosein Faidaei, Saeed Serayeshi. Some neutronic calculations for the VVER-1000 using WIMS and Citation code. Anirkabir University of Technology, Iran, 2009. (in English)
10. Amir Hosein Faidaei, Saeed Serayeshi. Control rod worth calculation for VVER-1000 using SRAC and MC NPS code. Institute nuclear science and Technology, Vietnam, 2012. (in English)
11. L. Thilagam, C. Sunil Sunny & K.V. Subbaiah. Doppler coefficient of reactivity calculation for different enrichment of uranium oxide. Safety research. Kalpakkam, India, 2000. (in English)
12. Gert. Jan Auwerda. Investigation of neutrons and heat transfer in gas core reactor, 2009. (in English)
13. Georgy L. Khorasanov, Anatoly P. Ivanov, Anatoly I. Blokhin. Neutronic and Physical Characteristics of the Ads CoreWith A Lead-208 Coolant. Institute for Physics and Power Engineering, 2007. (in English)
Review
For citations:
Xu Yu. Optimizing the Neutronic Parameters for VVER-1200 Reactor Core Using WIMS-ANLS Code. Global Nuclear Safety. 2018;1(1):87-95. (In Russ.) https://doi.org/10.26583/GNS-2018-01-09. EDN: XQXHDV
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