Power Burst Facility severe-fuel-damage test program. [PWR]
Conference
·
OSTI ID:6797093
As a result of the Three Mile Island Unit 2 (TMI-2) accident, the United States Nuclear Regulatory Commission (USNRC) has initiated a severe fuel damage research program to investigate fuel rod and core response, and fission product and hydrogen release and transport during degraded core cooling accidents. This paper presents a discussion of the expected benefits of the PBF severe fuel damage tests to the nuclear industry, a description of the first five planned experiments, the results of pretest analysis performed to predict the fuel bundle heatup for the first two experiments, and a discussion of Phase II severe fuel damage experiments. Modifications to the fission product detection system envisioned for the later experiments are also described.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6797093
- Report Number(s):
- EGG-M-06682; CONF-820967-1; ON: DE83000685
- Country of Publication:
- United States
- Language:
- English
Similar Records
Severe fuel damage test 1-1 results. [PWR]
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Overview of the PBF Severe-Fuel-Damage Program and results of the first test. [PWR]
Conference
·
Sat Dec 31 23:00:00 EST 1983
·
OSTI ID:6622920
Severe fuel-damage scoping test performance. [PWR]
Conference
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:5624709
Overview of the PBF Severe-Fuel-Damage Program and results of the first test. [PWR]
Conference
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:5756649
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
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FISSION PRODUCT RELEASE
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TANK TYPE REACTORS
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210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
DAMAGE
FISSION PRODUCT RELEASE
FUEL ASSEMBLIES
PBF REACTOR
PULSED REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
STRESSES
TANK TYPE REACTORS
TEMPERATURE GRADIENTS
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS