Published June 1979 | Version v1
Report Restricted

Fuel rod material behavior during Test PCM-1

Creators

Description

The analysis is presented of the fuel rod materials behavior based on the postirradiation examination of the Test PCM-1 fuel rod from the Power-Cooling-Mismatch (PCM) Test Series. The test objective was to evaluate the behavior of a single pressurized water reactor (PWR) type fuel rod subjected to film boiling operation at high power following rod failure. The failure mechanisms and subsequent breakup of the fuel and cladding are discussed. The fuel rod cladding temperature profile is determined by metallographic examination of cladding microstructures and calculations based on kinetic correlations of the cladding external surface reaction layers with the duration of film boiling. Cladding-coolant and cladding-fuel interactions are investigated by metallographic and microprobe examination and chemical analysis of the cladding. Fuel restructuring and chemical changes are also addressed

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A04/MF A01.

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Restricted

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Additional details

Additional titles

Augmented title (English)
PWR

Publishing Information

Imprint Pagination
67 p.
Report number
NUREG/CR--0757

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
11499790
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
FUEL CANS; FUEL ELEMENT FAILURE; FUEL RODS; FUEL-CLADDING INTERACTIONS; HEAT TRANSFER; MICROSTRUCTURE; PERFORMANCE TESTING; POWER-COOLING-MISMATCH ACCIDEN; PWR TYPE REACTORS; REACTOR SAFETY; THERMAL STRESSES; ZIRCALOY; ZIRCONIUM OXIDES
Descriptors DEC
ACCIDENTS; ALLOYS; CHALCOGENIDES; CRYSTAL STRUCTURE; ENERGY TRANSFER; FUEL ELEMENTS; OXIDES; OXYGEN COMPOUNDS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; STRESSES; TESTING; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENT COMPOUNDS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS; ZIRCONIUM COMPOUNDS

Optional Information

Secondary number(s)
TREE--1333.