Published September 1976
| Version v1
Report
Restricted
Responses to NRC questions concerning NJP-BWR ECCS evaluation model and application to the Oyster Creek Plant
Description
Requested additional information on the Exxon NJP-BWR ECCS evaluation model and its application to Oyster Creek-1 Reactor is presented
Availability note (English)
MF available from INIS under the Report Number.
Files
Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Pagination
- 51 p.
- Report number
- XN--75-55-(Rev.2)(Suppl.1)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8296489
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; ECCS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; MATHEMATICAL MODELS; OYSTER CREEK-1 REACTOR; REACTOR KINETICS
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; KINETICS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Exxon Nuclear Co., Inc., Richland, WA.