Published 1987 | Version v1
Report Open

A comparative study of STCP and SCDAP simulation of PBF SFD Test 1-1

Creators

Description

This paper presents the results of a detailed comparison of the Source Term Code Package (STCP) and the SCDAP computer codes for simulation of the Power Burst Facility (PBF) Severe Fuel Damage (SFD) test 1-1. The SCDAP code is mechanistic, and has been benchmarked against a wide range of severe accident data. The SFD 1-1 test was designed to simulate the heatup and resulting fuel damage in the upper half of a 3000-Mw(t) PWR core approximately 2 to 3 hours after initiation of a small break accident, when the core is approximately 75% uncovered. 6 refs., 1 fig

Availability note (English)

NTIS, PC A02/MF A01 - US Govt. Printing Office. as DE87011296.

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Additional details

Publishing Information

Imprint Pagination
6 p.
Report number
BNL-NUREG--39917

Conference

Title
Joint meeting of the American Nuclear Society and the Atomic Industrial Forum.
Dates
15-19 Nov 1987.
Place
Los Angeles, CA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
19023646
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTERIZED SIMULATION; FISSION PRODUCT RELEASE; FUEL ASSEMBLIES; HYDROGEN; LOSS OF COOLANT; PBF REACTOR; PWR TYPE REACTORS; REACTOR CORES; REACTOR SAFETY EXPERIMENTS; S CODES; SOURCE TERMS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; ELEMENTS; ENRICHED URANIUM REACTORS; NONMETALS; POWER REACTORS; PULSED REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SIMULATION; TANK TYPE REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-871101--19.