Summary of ORNL work on NRC-sponsored HTGR safety research, July 1974-September 1980
- Ball, S.J.
- Cleveland, J.C.
- Conklin, J.C.
- Delene, J.G.
- Harrington, R.M.
- Hatta, M.
- Hedrick, R.A.
- Johnson, L.G.
- Sanders, J.P.
DOIAbstract
A summary is presented of the major accomplishments of the Oak Ridge National Laboratory (ORNL) research program on High-Temperature Gas-Cooled Reactor (HTGR) safety. This report is intended to help the nuclear Regulatory Commission establish goals for future research by comparing the status of the work here (as well as at other laboratories) with the perceived safety needs of the large HTGR. The ORNL program includes extensive work on dynamics-related safety code development, use of codes for studying postulated accident sequences, and use of experimental data for code verification. Cooperative efforts with other programs are also described. Suggestions for near-term and long-term research are presented
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