Published August 1974 | Version v1
Report Restricted

Calculation of maximum fuel enthalpy during rod ejection accident

Creators

Description

Two methods of calculating maximum fuel enthalpy during a rod ejection accident are set forth. Examination of the relative conservatisms of the two methods reveals that the values of fuel enthalpy are well below the threshold value for prompt fuel failure regardless of the method used. This report is applicable to 177 fuel-assembly plants which have operating licenses or are expected to receive operating licenses in 1974. (6 references) (U.S.)

Availability note (English)

MF available from INIS under the Report Number.

Files

Restricted

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

Additional details

Additional titles

Augmented title (English)
PWR type reactors

Publishing Information

Imprint Pagination
14 p.
Report number
BAW--10081A

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
6213297
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
ENTHALPY; FUEL ELEMENTS; HEAT TRANSFER; PWR TYPE REACTORS; REACTOR SAFETY; ROD EJECTION ACCIDENTS; SPATIAL DISTRIBUTION
Descriptors DEC
ACCIDENTS; DISTRIBUTION; ENERGY TRANSFER; PHYSICAL PROPERTIES; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMODYNAMIC PROPERTIES; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Babcock and Wilcox, Lynchburg, VA.