Published July 1985 | Version v1
Report Metadata-only

Calculation of fission product release to the environment for some PWR core melt sequences

Creators

  • 1. Gesellschaft fuer Reaktorsicherheit (GRS)mbH, Koeln, West Germany

Description

Calculations of fission product release from the fuel, and for fission product transport and depletion within the containment are performed considering BIBLIS-B, a KWU-type 1300 MWe PWR. A large pipe break accident was analyzed, assuming ensued containment isolation, and failure of the emergency cooling recirculation system leading to late overpressure failure. The behavior of particulate fission products was calculated with the NAUA code taking into account the special plant design features: steel containment and surrounding annulus. A sensitivity analysis of the release to the environment reveals the influence of parameters such as primary mass release, agglomeration processes, leak rates, and geometry of the involved compartments

Additional details

Publishing Information

Imprint Title
American Nuclear Society meeting on fission-product behavior and source term research: proceedings
Journal Page Range
p. 67.1-67.13.
Report number
EPRI-NP--4113-SR

Conference

Title
Topical meeting on fission product behavior and source term research.
Dates
15-19 Jul 1984.
Place
Snowbird, UT (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
19023741
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
AEROSOLS; BIBLIS-B REACTOR; COMPACTING; COMPUTER CODES; CONTAINMENT BUILDINGS; ECCS; FAILURES; FISSION PRODUCT RELEASE; FORECASTING; HEAT TRANSFER; HYDRODYNAMICS; LEAKS; LOSS OF COOLANT; MELTDOWN; N CODES; PIPES; PROBABILITY; RADIOACTIVITY TRANSPORT; REACTOR ACCIDENTS; REACTOR CORE DISRUPTION; REACTOR CORES; REACTOR SAFETY; RUPTURES; SENSITIVITY ANALYSIS; TEMPERATURE DEPENDENCE
Descriptors DEC
ACCIDENTS; BUILDINGS; COLLOIDS; CONTAINMENT; DISPERSIONS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FABRICATION; FLUID MECHANICS; MECHANICS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; SOLS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS