The coupled kinetic and thermal-hydraulic three dimensional code system NLSANMT/COBRA-IV for PWR core transient analysis
Creators
- 1. Department of Nuclear Engineering,Xi'an Jiaotong University, Xi'an, Shaanxi 710049 (China)
Description
A three dimensional neutron kinetic nodal code NLSANMT has been developed based on the semi-analytical nodal expansion method and nonlinear iteration strategy, and it has been coupled with the subchannel thermal hydraulic core analysis code COBRA-IV to form the integrated code system NLSANMT/COBRA-IV for PWR core transient analysis. This paper describes the features and status of the integrated NLSANMT/COBRA-IV system. A demonstration application of the NLSANMT/COBRA-IV code to rod ejection accident analysis is presented using the OECD NEACRP PWR hot zero power full core rod ejection benchmark problem. The NLSANMT/COBRA-IV solution agrees well with the reference solution, even when one node per assembly and one channel per assembly are used.
Availability note (English)
Available from http://dx.doi.org/10.1016/S0306-4549(02)00077-4Additional details
Identifiers
- DOI
- 10.1016/S0306-4549(02)00077-4;
- arXiv
- arXiv:hep-ph/9902390v1;
- PII
- S0306454902000774;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 30
- Journal Issue
- 4
- Journal Page Range
- p. 405-412
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 50070227
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BENCHMARKS; COMPUTER CODES; MATHEMATICAL SOLUTIONS; NEA; NODAL EXPANSION METHOD; NONLINEAR PROBLEMS; PWR TYPE REACTORS; REACTOR KINETICS; ROD EJECTION ACCIDENTS; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- ACCIDENTS; CALCULATION METHODS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; INTERNATIONAL ORGANIZATIONS; KINETICS; MECHANICS; OECD; POWER REACTORS; REACTIVITY-INITIATED ACCIDENTS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.