Analysis of VVER-1000 fuel cycle using MCNPX code

被引：0

作者：

Huml, Ondrej ^{[1
]}

机构：

[1] Czech Tech Univ, FNSPE, Dept Nucl Reactors, Prague 18000 8, Czech Republic

来源：

PROCEEDINGS OF THE 13TH INTERNATIONAL SCIENTIFIC CONFERENCE ELECTRIC POWER ENGINEERING 2012, VOLS 1 AND 2 | 2012年

关键词：

MCNPX; VVER-1000; fuel cycle; depletion; EPE2012;

D O I：

暂无

中图分类号：

TE [石油、天然气工业]; TK [能源与动力工程];

学科分类号：

0807 ; 0820 ;

摘要：

Analysis and optimisation of power reactors fuel cycles is very actual topic. Deterministic or stochastic computer codes or their combination can be used for such fuel cycle analysis. This paper presents possibilities of the MCNPX stochastic code application for neutronic part of these analyses. The simulation is performed on VVER-1000 pressurised water reactor model with four-year equilibrium fuel cycle. Evolution of multiplication factor k(eff) and isotopic changes of used fuel were determined. Plutonium vector as a spent fuel quality indicator was also calculated. Some disadvantages of the code and material issues were observed and future improvements are mentioned in the paper.

引用

页码：1235 / 1239

页数：5

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