Published March 1980
| Version v1
Report
Restricted
Program requirements to determine and relate fuel damage and failure thresholds to anticipated conditions in pressurized water reactors
Description
Anticipated transients, licensing criteria, and damage mechanisms for PWR fuel rods are reviewed. Potential mechanistic fuel rod damage limits for PWRs are discussed. An expermental program to be conducted out-of-pile and in the Engineering Test Reactor (ETR) to generate a safety data base to define mechanistic fuel damage and failure thresholds and to relate these thresholds to the thermal-hydraulic and power conditions in a PWR is proposed. The requirements for performing the tests are outlined. Analytical support requirements are defined
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A06/MF A01.
Files
Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Pagination
- 121 p.
- Report number
- EGG-TFBP--5107
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11544144
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CRITICAL HEAT FLUX; FUEL RODS; PRESSURE GRADIENTS; PWR TYPE REACTORS; REACTOR SAFETY; SPATIAL DISTRIBUTION; THERMAL STRESSES; TRANSIENTS
- Descriptors DEC
- DISTRIBUTION; FUEL ELEMENTS; HEAT FLUX; REACTOR COMPONENTS; REACTORS; SAFETY; STRESSES; WATER COOLED REACTORS; WATER MODERATED REACTORS