Published March 1988 | Version v1
Report Restricted

Fission product release characteristics into containment under design basis and severe accident conditions

Creators

Description

A detailed review of the radiological release estimates for light water reactor accident sequences is presented as a basis for development of a simplified approach for prediction of characteristics of radiological releases into containments under design basis and severe accident conditions for both Pressurized Water Reactors (PWRs) and Boiling Water Reactors (BWRs). Resulting source term estimates are also compared with parallel results using the Source Term Code Package (STCP) methodology

Availability note (English)

NTIS, PC A06 - US Govt. Printing Office. as TI88010887.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Publishing Information

Imprint Pagination
105 p.
Report number
NUREG/CR--4881

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
19105013
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
AEROSOLS; BWR TYPE REACTORS; C CODES; CONCRETES; CONTAINMENT; CORIUM; DESIGN BASIS ACCIDENTS; FISSION PRODUCT RELEASE; HEAT TRANSFER; HYDRAULICS; I CODES; PWR TYPE REACTORS; RADIOACTIVE EFFLUENTS; REACTOR COOLING SYSTEMS; REACTOR CORE DISRUPTION; REACTOR SAFETY; S CODES; SOURCE TERMS
Descriptors DEC
ACCIDENTS; BUILDING MATERIALS; COLLOIDS; COMPUTER CODES; COOLING SYSTEMS; DISPERSIONS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; MATERIALS; POWER REACTORS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; SOLS; THERMAL REACTORS; WASTES; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
BNL-NUREG--52059.