Fast reactor safety testing in Transient Reactor Test (TREAT) in the 1980s
Conference
·
OSTI ID:6604391
- Argonne National Lab., IL (USA)
- Westinghouse Hanford Co., Richland, WA (USA)
- Argonne National Lab., Idaho Falls, ID (USA)
Several series of fast reactor safety tests were performed in TREAT during the 1980s. These focused on the transient behavior of full-length oxide fuels (US reference, UK reference, and US advanced design) and on modern metallic fuels. Most of the tests addressed fuel behavior under transient overpower or loss-of-flow conditions. The test series were the PFR/TREAT tests; the RFT, TS, CDT, and RX series on oxide fuels; and the M series on metallic fuels. These are described in terms of their principal results and relevance to analyses and safety evaluation. 4 refs., 3 tabs.
- Research Organization:
- Argonne National Lab., IL (USA)
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6604391
- Report Number(s):
- CONF-900804-32; ON: DE90017672; TRN: 91-010608
- Resource Relation:
- Conference: International topical meeting on fast reactor safety, Snowbird, UT (USA), 12-16 Aug 1990
- Country of Publication:
- United States
- Language:
- English
Similar Records
In-pile loss-of-flow TREAT test L05 with prototype fast reactor fuel
PFR/TREAT CO1 and LO1 experiments
First overpower tests of metallic IFR [Integral Fast Reactor] fuel in TREAT [Transient Reactor Test Facility]: Data and analysis from tests M5, M6, and M7
Technical Report
·
Sun Jan 01 00:00:00 EST 1984
·
OSTI ID:6604391
+5 more
PFR/TREAT CO1 and LO1 experiments
Conference
·
Fri Jan 01 00:00:00 EST 1982
·
OSTI ID:6604391
+6 more
First overpower tests of metallic IFR [Integral Fast Reactor] fuel in TREAT [Transient Reactor Test Facility]: Data and analysis from tests M5, M6, and M7
Technical Report
·
Fri Dec 01 00:00:00 EST 1989
·
OSTI ID:6604391
+2 more
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
MIXED OXIDE FUELS
NUCLEAR FUELS
LOSS OF FLOW
REACTOR SAFETY
TESTING
TRANSIENTS
TREAT REACTOR
ACCIDENTS
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
REACTOR ACCIDENTS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SOLID FUELS
SOLID HOMOGENEOUS REACTORS
TEST REACTORS
THERMAL REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
MIXED OXIDE FUELS
NUCLEAR FUELS
LOSS OF FLOW
REACTOR SAFETY
TESTING
TRANSIENTS
TREAT REACTOR
ACCIDENTS
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
REACTOR ACCIDENTS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SOLID FUELS
SOLID HOMOGENEOUS REACTORS
TEST REACTORS
THERMAL REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors