Evaluation of GCFR PCRV Containment Capability.
Abstract
An analytical evaluation of the containment capability of the Prestressed Concrete Reactor Vessel for the Gas Cooled Fast Breeder Reactor has been conducted. Displacement and stress predictions were made from NASTRAN finite element calculations which were consistent with static hydraulic loading tests of 1/20 scale PCRV models. This favorable comparison strengthens confidence in the results of NASTRAN calculations for static and transient loading of the full scale GCFR-PCRV. The NASTRAN results imply that a Core Disassembly Accident of 4000 MWsec thermal energy release should be contained by the PCRV with only moderate cracking at the inside of the lower haunch. This value should be substantiated by experiment before further analysis is performed.
Document Details
- Document Type
- Technical Report
- Publication Date
- Apr 15, 1977
- Accession Number
- ADA039908
Entities
People
- Joseph G. Connor Jr.
- Michael E. Giltrud
Organizations
- Naval Ordnance Laboratory