Fission product release from commercial versus simulated fuels in LWR (light water reactor) accident studies

Conference · Fri Jun 01 00:00:00 EDT 1990 · Transactions of the American Nuclear Society; (USA)

OSTI ID:6372850

Osborne, M F; Lorenz, R A; Collins, J L ^[1]; Albrecht, H

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1. Oak Ridge National Lab., TN (USA)

Experimental studies of fission product release from light water reactor (LWR) fuels have been conducted at Oak Ridge National Laboratory (ORNL). The principal objective of this project, which is supported by the US Nuclear Regulatory Commission (NRC), is to provide the fission product release data base for the severe-accident program that is required for sequence-dependent analyses. The results from these tests of commercial LWR fuel have been complemented by data from tests of simulated high-burnup fuel - unirradiated UO{sub 2} that contained fission product species in the forms and concentrations similar to the real fission products in irradiated fuel. Tests of simulated LWR fuel included both (a) the SASCHA project in the Federal Republic of Germany, which studied release from a simulated core melt of UO{sub 2}, Zircaloy, and stainless steel; and (b) tests of SASCHA-type fuel in the ORNL test apparatus. This review considers results in steam atmosphere from the SASCHA tests, the four ORNL tests of simulated fuel, and the first nine ORNL tests of highly irradiated fuel. Data from the ORNL simulated fuel tests and the three latest irradiated fuel tests have not been published previously.

• OSTI ID: 6372850
• Report Number(s): CONF-900608-; CODEN: TANSA; TRN: 91-008264
• Journal Information: Transactions of the American Nuclear Society; (USA), Vol. 61; Conference: American Nuclear Society (ANS) annual meeting, Nashville, TN (USA), 10-14 Jun 1990; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR SAFETY EXPERIMENTS
PWR TYPE REACTORS
REACTOR CORE DISRUPTION
FISSION PRODUCT RELEASE
BURNUP
FEDERAL REPUBLIC OF GERMANY
FISSION PRODUCTS
FUEL CANS
ORNL
RESEARCH PROGRAMS
SIMULATION
STAINLESS STEELS
STEAM
URANIUM DIOXIDE
US NRC
ZIRCALOY
ACCIDENTS
ACTINIDE COMPOUNDS
ALLOYS
CHALCOGENIDES
EUROPE
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
MATERIALS
NATIONAL ORGANIZATIONS
OXIDES
OXYGEN COMPOUNDS
RADIOACTIVE MATERIALS
REACTOR ACCIDENTS
REACTORS
STEELS
URANIUM COMPOUNDS
URANIUM OXIDES
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WESTERN EUROPE
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled