Published 2005 | Version v1
Miscellaneous Metadata-only

Fission products transport in CANDU Primary Heat Transport System in a severe accident

Creators

  • 1. Institute for Nuclear Research, INR, PO Box 78, 1 Campului Street, RO-115400 Mioveni, Jud. Arges (Romania)

Description

The paper is intended to analyse the distribution of the fission products (FPs) in CANDU Primary Heat Transport (PHT) by using the ASTEC code (Accident Source Term Evaluation Code). The data related to the nodes' definitions, temperatures and pressure conditions were chosen as possible as real data from CANDU NPP loss of coolant accident sequence. Temperature and pressure conditions during the accident was calculated by CATHENA code and the source term of FPs (introduced into the PHT) was estimated by ORIGEN code. The results consists of mass distributions in the circuit nodes and the transferred mass to the containment through the break for different species (FPs and chemical species). (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) or University Politehnica of Bucharest, Splaiul Independentei 313, Sector 6, RO-77206 Bucharest (RO)
Part of:
International Symposium on Nuclear Energy SIEN 2005, Nuclear Power - A New Challenge

Additional details

Identifiers

URL
https://www.nuclearelectrica.ro/;

Publishing Information

Publisher
Romanian Nuclear Energy Association, AREN
Imprint Place
Bucharest (Romania)
Imprint Title
International Symposium on Nuclear Energy SIEN 2005, Nuclear Power - A New Challenge
Imprint Pagination
643 p.
Journal Page Range
p. P15.1-P15.8

Conference

Title
international symposium on nuclear energy, nuclear power - a new challenge
Acronym
SIEN 2005
Dates
23-27 Oct 2005
Place
Bucuresti (Romania)

INIS

Country of Publication
Romania
Country of Input or Organization
Romania
INIS RN
37019873
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
A CODES; C CODES; CANDU TYPE REACTORS; FISSION PRODUCTS; FUEL CHANNELS; HEAT TRANSFER; LOSS OF COOLANT; MASS DISTRIBUTION; O CODES; PRIMARY COOLANT CIRCUITS; REACTOR ACCIDENTS; SENSITIVITY ANALYSIS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; DISTRIBUTION; ENERGY SYSTEMS; ENERGY TRANSFER; HEAVY WATER MODERATED REACTORS; ISOTOPES; MATERIALS; POWER REACTORS; PRESSURE TUBE REACTORS; RADIOACTIVE MATERIALS; REACTOR ACCIDENTS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SPATIAL DISTRIBUTION; THERMAL REACTORS

Optional Information

Notes
5 refs., 6 figs., 3 tabs.