Progress and future plans in the PFR/TREAT safety testing programs

Conference · Wed Jan 01 00:00:00 EST 1986

OSTI ID:5507664

Alter, H; Cowking, C B; Klickman, A E; Wood, M H

This paper briefly describes the progress to date on the joint UKAEA/USDOE program of fast reactor fuel safety testing and the definition of the future tests. The program involves transient tests in the TREAT reactor on fresh and irradiated mixed fuel pins. The tests simulate transient overpower (TOP) accidents, which result from an unintentional addition of reactivity and transient undercooling followed by overpower (TUCOP) accidents, which arise from an unintentional stoppage of the primary sodium circulating pumps, both with failure to scram. Thirteen tests have been performed to date, all on UK pins. Future plans include five tests, all on US pins which have been irradiated in FFTF. Much has been learned about the behavior of fuel driven to conditions well beyond those existing during normal reactor operation.

• Research Organization: Argonne National Lab., IL (USA); UKAEA Risley Nuclear Power Development Establishment; UKAEA Atomic Energy Establishment, Winfrith
• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 5507664
• Report Number(s): CONF-860501-15; ON: DE86014494
• Resource Relation: Conference: Conference on the science and technology of fast reactor safety, Channel Islands, UK, 12 May 1986
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
MIXED OXIDE FUELS
RESEARCH PROGRAMS
TESTING
PFR REACTOR
TREAT REACTOR
FFTF REACTOR
IRRADIATION
LMFBR TYPE REACTORS
NUCLEAR FUELS
REACTOR SAFETY
TEST FACILITIES
AIR COOLED REACTORS
BREEDER REACTORS
ENERGY SOURCES
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUELS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HOMOGENEOUS REACTORS
LIQUID METAL COOLED REACTORS
MATERIALS
POWER REACTORS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SODIUM COOLED REACTORS
SOLID FUELS
SOLID HOMOGENEOUS REACTORS
TEST REACTORS
THERMAL REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
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220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors