Global Nuclear Safety
National Research Nuclear University "MEPhI"
online version: ISSN 2499-9733
print version: ISSN 2305-414Х
2018-1(26)
Design, manufacturing and commissioning of nuclear industry equipment
| Article Name | Optimizing the Neutronic Parameters for VVER-1200 Reactor Core Using WIMS-ANLS Code |
|---|---|
| Authors | Yubin Xu |
| Address | National Research Tomsk Polytechnic University, Institute of Physics |
| 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%). |
| Keywords | VVER-1200, WIMS-ANL; lattice cell, fuel assembly, neutronic characteristics, reactivity, effective multiplication factor, reactivity |
| Language | Russian |
| 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) |
| Papers | 87 - 95 |
| URL Article | URL Article |
| Open Article |