Fracture mechanics of thin wall cylindrical pressure vessels: an interim review
Description
The report is a result of activities in the LMFBR Fuel Rod Transient Performance Program sponsored by the LMFBR Branch of the Division of Project Management, U.S. Nuclear Regulatory Commission. One of the objectives is to develop predictions relative to the length, direction, and rate of growth of cladding rips subsequent to (or concurrent with) the initial cladding breach during unprotected transients. To provide a basis for evaluation, Battelle, Pacific Northwest Laboratories has reviewed most available fracture mechanics assessments relative to thin-wall cylindrical pressure vessels. The purpose of the report is to review the various fracture mechanics models and to describe the pertinent fracture parameters. It is intended to provide a formal basis for assessing future analytical predictions of fracture behavior of materials exposed to transient LMFBR thermal and mechanical loading conditions. In addition, the report is expected to provide reference material for evaluating or developing experimental programs required to properly address the problem of predicting fracture behavior of materials during transient events
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01.
Files
Additional details
Additional titles
- Augmented title (English)
- LMFBR
Publishing Information
- Imprint Pagination
- 40 p.
- Report number
- PNL--2417
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 9389365
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- EXCURSIONS; FRACTURE PROPERTIES; FUEL CANS; FUEL ELEMENT FAILURE; FUEL RODS; LMFBR TYPE REACTORS; MATHEMATICAL MODELS; PERFORMANCE TESTING
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUEL ELEMENTS; LIQUID METAL COOLED REACTORS; MECHANICAL PROPERTIES; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; TESTING