Analysis of a VVER-1000 in-core fuel management benchmark with DRAGON and DONJON

被引：0

作者：

Van Rooijen W.F.G. ^{[1
]}

Khan M.J.H. ^{[2
]}

Hébert A. ^{[3
]}

Salino V. ^{[4
]}

机构：

[1] Research Institute of Nuclear Engineering, University of Fukui, Kannawa-cho 1-2-4, Tsuruga-shi, Fukui-ken

[2] Atomic Energy Research Establishment, Ganakbari, Savar, GPO BOX #3787, Dhaka

[3] Ecole Polytechnique de Montréal, Institut de Génie Nucléaire, P.O. Box 6079, Station Centre-Ville, Montréal, H3C 3A7, QC

[4] Institut de Radioprotection et Sûreté Nucléaire (IRSN), PSN-EXP, SNC, LNR, Fontenay-aux-Roses

来源：

International Journal of Nuclear Energy Science and Technology | 2017年 / 11卷 / 04期

关键词：

DONJON; DRAGON; IAEA VVER benchmark; Rooppur nuclear power plant; VVER core analysis; VVER core calculation; VVER core follow simulation; VVER lattice calculation; VVER-1000;

D O I：

10.1504/IJNEST.2017.090658

中图分类号：

学科分类号：

摘要：

This paper discusses the calculation of the IAEA benchmark entitled In-core fuel management code package validation for WWERs (IAEA-TECDOC-847) with the Version5 code system (DRAGON and DONJON). Calculations were performed for VVER-1000 cores. Cell calculations are done with DRAGON. Core calculations are done with DONJON, using CLE-2000 procedures to determine the reactor state at each depletion step, taking into account the control rod insertion pattern, reactor power, coolant inlet temperature and coolant mass flow. A multi-variate cross-section database for the core calculations is made with DRAGON. Calculated results are the critical boron concentration at each depletion step, and axial and radial power profiles at a few depletion steps. The present work serves as a feasibility study for the application of DRAGON and DONJON to VVER cores, and results are generally acceptable. Suggestions are made to improve the quality of the simulations. © 2017 Inderscience Enterprises Ltd.

引用

页码：345 / 376

页数：31

共 7 条

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[5] In-Core Fuel Management Code Package Validation for WWERs, (1995)
[6] Marleau G., Hebert A., Roy R., A User Guide for DRAGON Version5, (2016)
[7] Nagaya Y., Okumura K., Mori T., Nakagawa M., MVP/GMVP-II: General purpose Monte Carlo codes for neutron and photon transport calculations based on continuous energy and multigroup methods, Japan Atomic Energy Research Institute, (2005)

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