Published February 2010 | Version v1
Report Metadata-only

Simplified approach to dynamic process modelling. Annex 4

Creators

  • 1. Institute of Physics and Power Engineering (Russian Federation)

Description

This document presents the OKBM contribution to the analysis of a benchmark of BN-600 reactor hybrid core with simultaneous loading of uranium fuel and MOX within the framework of the international IAEA Co-ordinated Research Project 'Updated Codes and Methods to Reduce the Calculational Uncertainties of the LMFR Reactivity Effects'. In accordance with Action 12 defined during the second RCM, the simplified transient analysis was carried out on the basis of the reactivity coefficients sets, presented by all CRP participants. Purpose of present comparison is the evaluation of spread in the basic transient parameters in connection with spread in the used reactivity coefficients. A ULOF accident initial stage on the simplified model was calculated by using the SAS4A code

Part of:
BN-600 hybrid core benchmark analyses. Results from a coordinated research project on updated codes and methods to reduce the calculational uncertainties of the LMFR reactivity effects

Additional details

Identifiers

URL
http://www-pub.iaea.org/MTCD/publications/PDF/te_1623_web.pdf; http://www-pub.iaea.org/MTCD/publications/publications.asp;

Publishing Information

ISBN
978-92-0-109409-4
Imprint Title
BN-600 hybrid core benchmark analyses. Results from a coordinated research project on updated codes and methods to reduce the calculational uncertainties of the LMFR reactivity effects
Imprint Pagination
309 p.
Journal Page Range
p. 202-214
ISSN
1011-4289
Report number
IAEA-TECDOC--1623

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
41043062
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
BELOYARSK-3 REACTOR; BENCHMARKS; COMPARATIVE EVALUATIONS; IAEA; MIXED OXIDE FUELS; REACTIVITY; REACTIVITY COEFFICIENTS; REACTOR ACCIDENTS; SIMULATION; TRANSIENTS; URANIUM
Descriptors DEC
ACCIDENTS; ACTINIDES; BREEDER REACTORS; ELEMENTS; ENERGY SOURCES; EPITHERMAL REACTORS; EVALUATION; FAST REACTORS; FBR TYPE REACTORS; FUELS; INTERNATIONAL ORGANIZATIONS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS; METALS; NUCLEAR FUELS; POWER REACTORS; REACTOR MATERIALS; REACTORS; SODIUM COOLED REACTORS; SOLID FUELS

Optional Information

Notes
16 figs, 3 tabs