Published May 23, 2001 | Version v1
Report

MARS Development Program and Progress

  • 1. Korea Atomic Energy Research Institute, Dukjin 150, Yusung, Taejeon, 305-353 (Korea, Republic of)

Description

MARS (Multi-dimensional Analysis of Reactor Safety) code is being developed by KAERI for the realistic thermal-hydraulic system analysis of light water reactor transients. The MARS development program consists of two stages of code development. MARS 1.4 is a unified code of RELAPS and COBRA-TF and has been developed as a basic code frame for the multi-dimensional thermal-hydraulic system analysis. And, MARS 2.x is being developed as a multi-purpose system analysis code for the coupled analysis of multi-dimensional system thermal-hydraulics, 3D core kinetics, CHF and containment. This paper discusses the MARS development program and the progress focusing on the new features of the code, that is, code unification, code modernization and restructuring, code assessment and code coupling. It also briefly introduces KAERI experimental activities for T/H model development and safety confirmation. (authors)

Part of:
Proceedings of the workshop on advanced thermal-hydraulic and neutronic codes: current and future applications

Additional details

Publishing Information

Imprint Title
Proceedings of the workshop on advanced thermal-hydraulic and neutronic codes: current and future applications
Imprint Pagination
723 p.
Journal Page Range
p. 606-619
Report number
NEA-CSNI-R--2001-2

Conference

Title
current and future applications
Acronym
Workshop on advanced thermal-hydraulic and neutronic codes
Dates
10-13 Apr 2000
Place
Barcelona (Spain)

INIS

Country of Publication
Nuclear Energy Agency of the OECD (NEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
39036598
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONTAINMENT; KAERI; MANY-DIMENSIONAL CALCULATIONS; REACTOR SAFETY; SYSTEMS ANALYSIS; THERMAL HYDRAULICS; TRANSIENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Descriptors DEC
FLUID MECHANICS; HYDRAULICS; KOREAN ORGANIZATIONS; MECHANICS; NATIONAL ORGANIZATIONS; REACTORS; SAFETY

Optional Information

Notes
14 refs.