학술논문
Benchmark study of 10 MWthMaterial Test Reactor by standard deterministic codes
Document Type
Article
Source
Life Cycle Reliability and Safety Engineering; 20240101, Issue: Preprints p1-13, 13p
Subject
Language
ISSN
25201352; 25201360
Abstract
A static, full core calculation for IAEA 10 MWthMaterial Test Reactor (MTR) benchmark problem is carried out using a standard set of computer code systems, namely: (i) WIMSD/4, TWOTRAN and NEMSQR and (ii) DRAGON and NEMSQR. The current work focuses on the evaluation of various important neutronic parameters such as neutron multiplication factor, reactivity feedback coefficients, reactivity worth of control devices, etc. of the IAEA 10 MWthMTR benchmark reactor, using the above code systems. The IAEA 10 MWthbenchmark problem is useful for testing the ability of a code to reliably simulate a compact, highly heterogeneous core made up of U235-enriched fuel in plate-type geometry. The study is carried out to validate the calculation methodology currently adopted by us for plate-type fuel assemblies and compact reactor cores while using these standard computer codes.