Published 1982
| Version v1
Report
Restricted
Degraded core studies at INEL
Description
During 1980, planning of prototypical severe fuel damage tests to be conducted in the Power Burst Facility (PBF) to investigate fuel behavior in severe accidents up to temperatures of 24000K was initiated. This first series of tests is designated Phase I. Also, a code development effort was initiated to provide a reliable predictive tool for core behavior during severe accidents. During 1981, an assessment of capabilities and preliminary planning were begun for an in-pile experimental program to investigate the behavior of larger arrays of previously irradiated fuel rods at temperatures through UO2 melting. This latter series of tests is designated Phase II
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01 as DE82018738.
Files
Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Pagination
- 5 p.
- Report number
- EGG-M--01082
Conference
- Title
- American Nuclear Society annual meeting.
- Dates
- 6 - 11 Jun 1982.
- Place
- Los Angeles, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14724031
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; CORIUM; FUEL ELEMENT FAILURE; FUEL RODS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR CORES; REACTOR SAFETY; THERMAL STRESSES; URANIUM DIOXIDE
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; CHALCOGENIDES; FUEL ELEMENTS; OXIDES; OXYGEN COMPOUNDS; REACTOR COMPONENTS; REACTORS; SAFETY; STRESSES; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-820609--65.