Published 2009 | Version v1
Computer medium Metadata-only

Review of SCDAP/RELAP5 Code Application to severe accident analysis of CANDU Reactors

Creators

  • 1. Power Plant Engineering Faculty, Politehnica University, 313 Splaiul Independentei, sect. 6, RO-060042 Bucharest (Romania)
  • 2. Institute for Nuclear Research, PO Box 78, Campului 1, RO-115400 Pitesti-Mioveni (Romania)

Description

SCDAP/RELAP5 code has been developed in US for best-estimate simulation of light water reactors transients during nuclear accidents. The code models the coupled behaviour of the cooling system, reactor core and fission products release during the accident. It is the result of the coupling between RELAP5, modelling thermal hydraulic, control system, reactor kinetics and the transport of noncondensable gases, and SCDAP code modelling the behaviour of the reactor core during severe accidents. The paper briefly presents the application of SCDAP/RELAP5 code to CANDU severe accident analysis. Also, the paper proposes a summary of the needs for development that could enhance the quality of the severe accidents related predictions in CANDU reactors. (authors)

Availability note (English)

Available from author(s) or as a CD-ROM issued by Romanian Nuclear Energy Association, AREN, Str. Atomistilor 111, PO Box 53, RO-76900 Bucharest - Magurele (RO)
Part of:
International Symposium on Nuclear Energy SIEN 2009. Nuclear Power - A New Challenge

Additional details

Publishing Information

Publisher
Romanian Nuclear Energy Association, AREN
Imprint Place
Bucharest (Romania)
Imprint Title
International Symposium on Nuclear Energy SIEN 2007. Nuclear Power - A New Challenge
Imprint Pagination
532 p.
Journal Page Range
p. S3.240-S3.247

Conference

Title
international symposium on nuclear energy. Nuclear power - a new challenge
Acronym
SIEN 2009
Dates
12-16 Oct 2009
Place
Bucuresti (Romania)

INIS

Country of Publication
Romania
Country of Input or Organization
Romania
INIS RN
42076184
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CANDU TYPE REACTORS; FISSION PRODUCT RELEASE; GAS CONDENSATES; LOSS OF COOLANT; REACTOR CONTROL SYSTEMS; REACTOR COOLING SYSTEMS; REACTOR CORE DISRUPTION; REACTOR KINETICS; S CODES; THERMAL HYDRAULICS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; CONDENSATES; CONTROL SYSTEMS; COOLING SYSTEMS; ENERGY SYSTEMS; FLUID MECHANICS; FLUIDS; HEAVY WATER MODERATED REACTORS; HYDRAULICS; KINETICS; LIQUIDS; MECHANICS; NATURAL GAS LIQUIDS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS

Optional Information

Notes
17 refs., 6 figs., 2 tabs.