Behavior of irradiated LWR fuel pellets during thermal transients

Conference · Wed Jan 01 04:00:00 EST 1975

OSTI ID:4158087

Kelman, L R; Rest, J; Seitz, M G; Gehl, S M

Prediction of the behavior of LWR fuel rods and fission products under off-normal and accident conditions requires a physically realistic description of fuel swelling and fission-product release that currently does not exist. To satisfy this need, a program was initiated at ANL approximately a year ago with the prime objective of developing a comprehensive computer-base model that describes the release of fission products as a function of thermal transients anticipated in hypothetical accident situations. This model will be incorporated into ANC's FRAP accident-analysis code system. The analytical effort is supported by data developed from characterization of irradiated LWR fuel and from out-of-reactor transient heating tests of irradiated LWR fuel under conditions that simulate hypothetical LWR accidents. (auth)

• Research Organization: Argonne National Lab., Ill. (USA)
• DOE Contract Number: W-31109-ENG-38
• NSA Number: NSA-33-006685
• OSTI ID: 4158087
• Report Number(s): CONF-750958--2
• Country of Publication: United States
• Language: English

Related Subjects

*BWR TYPE REACTORS-- REACTOR ACCIDENTS
*FUEL PELLETS-- FISSION PRODUCT RELEASE
*PWR TYPE REACTORS-- REACTOR ACCIDENTS
210100* --Nuclear Power Plants--Power Reactors
Non- Breeding
Light-Water Moderated
Boiling Water Cooled
COMPUTER CODES
MATHEMATICAL MODELS
N77100* --Reactors--Power Reactors
Non-breeding
Light- water Moderated
Boiling Water-cooled
N77200 --Reactors--Power Reactors
Non-breeding
Light-water Moderated
Non-boiling Water-cooled
TRANSIENTS