Primary pipe rupture accident analysis for the Clinch River Breeder Reactor [electronic resource]
In this report, the thermal transient response of the CRBR to a severe primary coolant flow perturbation, initiated by a rupture of the primary heat transport system piping, is analyzed. This hypothetical accident is studied under the further assumption that the plant protection system does function...
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| Online Access: |
Online Access |
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| Corporate Author: | |
| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Upton, N.Y. : Oak Ridge, Tenn. :
Brookhaven National Laboratory ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
1976.
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| Subjects: |
| Summary: | In this report, the thermal transient response of the CRBR to a severe primary coolant flow perturbation, initiated by a rupture of the primary heat transport system piping, is analyzed. This hypothetical accident is studied under the further assumption that the plant protection system does function according to current design descriptions for the CRBR. Although a brief discussion of an unprotected (no scram) pipe rupture accident is presented, the major emphasis of the present report is on the protected accident. |
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| Item Description: | Published through SciTech Connect. 04/01/1976. "bnl-nureg-21656" Bari, R.A.; Albright, D.C. |
| Physical Description: | Pages: 174 : digital, PDF file. |