Published December 2003 | Version v1
Report Open

Development of a computer code for Dalat research reactor transient analysis

Creators

  • 1. Nuclear Research Institute, Dalat (Viet Nam)

Description

DRSIM (Dalat Reactor SIMulation) computer code has been developed for Dalat reactor transient analysis. It is basically a coupled neutronics-hydrodynamics-heat transfer code employing point kinetics, one dimensional hydrodynamics and one dimensional heat transfer. The work was financed by VAEC and DNRI in the framework of institutional R and D programme. Some transient problems related to reactivity and loss of coolant flow was carried out by DRSIM using temperature and void coefficients calculated by WIMS and HEXNOD2D codes. (author)

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Part of:
The VAEC - Annual report for 2001 - 2002

Additional details

Publishing Information

Imprint Title
The VAEC - Annual report for 2001 - 2002
Imprint Pagination
417 p.
Journal Page Range
p. 65-68
Report number
VAEC-AR--01/02

INIS

Country of Publication
Viet Nam
Country of Input or Organization
Viet Nam
INIS RN
35095824
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Progress Report
Descriptors DEI
COMPUTER CODES; COMPUTERIZED SIMULATION; HEAT TRANSFER; LOSS OF COOLANT; NUMERICAL ANALYSIS; ONE-DIMENSIONAL CALCULATIONS; PROGRESS REPORT; REACTIVITY; TRANSIENTS; TRIGA-2-DALAT REACTOR; VOID COEFFICIENT
Descriptors DEC
ACCIDENTS; DOCUMENT TYPES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MATHEMATICS; REACTIVITY COEFFICIENTS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION; SOLID HOMOGENEOUS REACTORS; THERMAL REACTORS; TRIGA TYPE REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
(VAEC-AR--01/02-5); 3 figs., 8 refs.