Published June 1985 | Version v1
Report Restricted

Evaluation of coolable geometry adequacy of the LWBR core during a loss-of-coolant accident (LOCA) (LWBR Development Program)

Creators

Description

Predictions of coolable geometry adequacy of the Light Water Breeder Reactor (LWBR) core during a hypothetical loss of coolant accident (LOCA) required development of appropriate analysis methods because of the differences between LWBR and current commercial power reactor designs. These differences include thoria-based fuel, thin-walled cladding, and close rod-rod spacing. The analysis methods and their application to LWBR are described for a postulated worst-case combined LOCA-seismic event. Fuel rod behavior is evaluated with respect to maintenance of coolable geometry, which is one of the acceptance criteria specified by the Nuclear Regulatory Commission

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A05/MF A01; 1 as DE85015069.

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Additional details

Publishing Information

Imprint Pagination
76 p.
Report number
WAPD-TM--1397

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
17007094
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
FUEL RODS; LOSS OF COOLANT; LWBR TYPE REACTORS; SEISMIC EFFECTS
Descriptors DEC
ACCIDENTS; BREEDER REACTORS; FUEL ELEMENTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS