Published 1990 | Version v1
Report Open

MELCOR modeling of the PBF [Power Burst Facility] Severe Fuel Damage Test 1-4

Creators

Description

This paper describes a MELCOR Version 1.8 simulation of the Power Burst Facility (PBF) Severe Fuel Damage (SFD) Test 1--4. The input data for the analysis were obtained from the Test Results Report and from SCDAP/RELAP5 input. Results are presented for the transient liquid level in the test bundle, clad temperatures, shroud temperatures, clad oxidation and hydrogen generation, bundle geometry changes, fission product release, and heat transfer to the bypass flow. Comparisons are made with experimental data and with SCDAP/RELAP5 calculations. 10 refs., 7 figs

Availability note (English)

MF available from INIS under the Report Number; OSTI as DE90016318; NTIS; INIS; US Govt. Printing Office Dep.

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Additional details

Publishing Information

Imprint Pagination
6 p.
Report number
BNL-NUREG--44503

Conference

Title
Probabilistic safety assessment and management.
Dates
4-7 Feb 1991.
Place
Beverly Hills, CA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
22032102
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S61: RADIATION PROTECTION AND DOSIMETRY;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; EXPERIMENTAL DATA; FISSION PRODUCT RELEASE; FUEL CANS; FUEL ELEMENTS; HEAT TRANSFER; HYDRAULICS; HYDROGEN; M CODES; PBF REACTOR; R CODES; REACTOR ACCIDENTS; REACTOR SAFETY; S CODES; SOURCE TERMS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; DATA; ELEMENTS; ENERGY TRANSFER; INFORMATION; NONMETALS; NUMERICAL DATA; PULSED REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; SIMULATION; TANK TYPE REACTORS

Optional Information

Contract/Grant/Project number
Contract AC02-76CH00016
Secondary number(s)
CONF-910213--6.