A transient overpower experiment in EBR-II

Conference · Tue Mar 01 00:00:00 EST 1994

OSTI ID:10129533

Herzog, J P; Tsai, H; Dean, E M ^[1]; Aoyama, T; Yamamoto, K ^[2]

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1. Argonne National Lab., IL (United States)
2. Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan)

The TOPI-IE test was a transient overpower test on irradiate mixed-oxide fuel pins in the Experimental Breeder Reactor-II (EBR-II). The test, the fifth in a series, was part of a cooperative program between the US Department of Energy and the Power Reactor and Nuclear Fuel Development Corporation of Japan to conduct operational transient testing on mixed-oxide fuel pins in the metal-fueled EBR-II. The principle objective of the TOPI-1E test was to assess breaching margins for irradiated mixed-oxide fuel pins over the Plant Protection System (PPS) thresholds during a slow, extended overpower transient. This paper describes the effect of the TOPI-1E experiment on reactor components and the impact of the experiment on the long-term operability of the reactor. The paper discusses the role that SASSYS played in the pre-test safety analysis of the experiment. The ability of SASSYS to model transient overpower events is detailed by comparisons of data from the experiment with computed reactor variables from a SASSYS post-test simulation of the experiment.

• Research Organization: Argonne National Lab., IL (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 10129533
• Report Number(s): ANL/RA/CP-80023; CONF-940402-8; ON: DE94007625; TRN: 94:008453
• Resource Relation: Conference: International topical meeting on the safety of advanced reactors,Pittsburgh, PA (United States),18-20 Apr 1994; Other Information: PBD: [1994]
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
FUEL PINS
TESTING
REACTOR COMPONENTS
LMFBR TYPE REACTORS
EXCURSIONS
MIXED OXIDE FUELS
FAILURES
REACTOR SAFETY
COORDINATED RESEARCH PROGRAMS
S CODES
EBR-2 REACTOR
TRANSIENTS
220900
210500
990200
POWER REACTORS
BREEDING
MATHEMATICS AND COMPUTERS