Fission product release and fuel behavior of irradiated light water reactor fuel under severe accident conditions

Technical Report · Fri Nov 01 00:00:00 EST 1991

OSTI ID:5905797

Allen, M D; Stockman, H W; Reil, K O ^[1]; Fisk, J W ^[2]

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1. Sandia National Labs., Albuquerque, NM (United States)
2. Tills (Jack) and Associates, Inc., Albuquerque, NM (United States)

The annular Core Research Reactor (ACRR) Source Term (ST) Experiment program was designed to obtain time-resolved data on the release of fission products from irradiated fuels under well-controlled light water reactor severe accident conditions. The ST-1 Experiment was the first of two experiments designed to investigate fission product release. ST-1 was conducted in a highly reducing environment at a system pressure of approximately 0.19 MPa, and at maximum fuel temperatures of about 2490 K. The data will be used for the development and validation of mechanistic fission product release computer codes such as VICTORIA.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; Sandia National Labs., Albuquerque, NM (United States)
• Sponsoring Organization: USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 5905797
• Report Number(s): NUREG/CR-5345; SAND-89-0308; ON: TI92004726
• 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
FUEL ELEMENTS
FISSION PRODUCT RELEASE
PWR TYPE REACTORS
ACPR REACTOR
EXPERIMENTAL DATA
FISSION PRODUCTS
IRRADIATION
POST-IRRADIATION EXAMINATION
RADIOISOTOPES
REACTOR ACCIDENTS
REACTOR SAFETY
SOURCE TERMS
TEST FACILITIES
V CODES
ACCIDENTS
COMPUTER CODES
DATA
ENRICHED URANIUM REACTORS
HOMOGENEOUS REACTORS
HYDRIDE MODERATED REACTORS
INFORMATION
ISOTOPES
MATERIALS
MIXED SPECTRUM REACTORS
NUMERICAL DATA
POWER REACTORS
PULSED REACTORS
RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SOLID HOMOGENEOUS REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220502* - Nuclear Reactor Technology- Environmental Aspects- Radioactive Effluents
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors