Skip to main content
OSTI.GOVU.S. Department of Energy Office of Scientific and Technical Information
U.S. Department of Energy
Office of Scientific and Technical Information
 

Postirradiation examination results from the LP-FP-2 center fuel module

Conference ·
OSTI ID:7176153
;
The LP-FP-2 experiment was conducted on July 9, 1985 in the Loss of Fluid Test (LOFT) facility located at the Idaho National Engineering Laboratory (INEL). The primary purpose of this experiment was to provide information of the release, transport, and deposition of fission products and aerosols during a sever core damage event performed in a large scale nuclear reactor facility. Postirradiation nondestructive and destructive examinations of the fuel bundle provided information to assist in achieving this objective, as well as providing information on the material behavior and interactions that occurred within the fuel bundle during this sever core damage experiment. This was a large-scale integral test, incorporating an 11 {times} 11 array of fuel rods, control rods, and instrumentation tubes, with an active core length of 1.68 m. Peak temperatures in the fuel bundle exceeded 2100 K or approximately 4.5 min, with localized peak temperatures exceeding the melting point of the UO{sub 2} fuel (3120 K). Large amounts of zircaloy oxidation and material relocation occurred during the experiment. The transient phase was terminated by a rapid reflood of cooling water, which resulted in significant oxidation and hydrogen generation. Zircaloy oxidation during the reflood period caused a rapid temperature excursion to occur in the upper two-thirds of the fuel bundle. This article summarizes the data and analysis from the postirradiation examinations of the LP-FP-2 fuel bundle. 12 refs., 39 figs., 8 tabs.
Research Organization:
EG and G Idaho, Inc., Idaho Falls, ID (USA)
Sponsoring Organization:
DOE/NE
DOE Contract Number:
AC07-76ID01570
OSTI ID:
7176153
Report Number(s):
EGG-M-90152; CONF-9005179--2; ON: DE90012966
Country of Publication:
United States
Language:
English

Similar Records

Summary of important results and SCDAP/RELAP5 analysis for OECD LOFT experiment LP-FP-2
Technical Report · Thu Mar 31 23:00:00 EST 1994 · OSTI ID:10147963
Hydrogen generation behavior in the LOFT FP-2 and other experiments; Comparative assessment for mitigated severe accident conditions
Journal Article · Tue Dec 31 23:00:00 EST 1991 · Nuclear Technology; (United States) · OSTI ID:5777159
Assessment of core damage models in SCDAP/RELAP5 during OECD LOFT LP-FP-2
Conference · Mon Dec 30 23:00:00 EST 1991 · OSTI ID:10164710

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220502 -- Nuclear Reactor Technology-- Environmental Aspects-- Radioactive Effluents
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
AEROSOLS
ALLOYS
CHALCOGENIDES
CHEMICAL ANALYSIS
COLLOIDS
CONTROL ELEMENTS
CORIUM
DATA
DESTRUCTIVE TESTING
DISPERSIONS
ELEMENTS
ENERGY TRANSFER
EXPERIMENTAL DATA
FISSION PRODUCT RELEASE
FISSION PRODUCTS
FLUID MECHANICS
FUEL ASSEMBLIES
FUEL CANS
HEAT TRANSFER
HYDRAULICS
HYDROGEN
INFORMATION
ISOTOPES
LOFT REACTOR
MATERIALS
MATERIALS TESTING
MECHANICS
MELTDOWN
NONDESTRUCTIVE ANALYSIS
NONMETALS
NUMERICAL DATA
OXIDES
OXYGEN COMPOUNDS
POST-IRRADIATION EXAMINATION
PWR TYPE REACTORS
RADIOACTIVE MATERIALS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SOLS
TANK TYPE REACTORS
TEMPERATURE MEASUREMENT
TEST REACTORS
TESTING
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS