Published October 1974
| Version v1
Report
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Development of models for the evaluation of temperatures in a HTGR core following a loss of forced circulation and simultaneous reactor trip
Description
no abstract available
Availability note (English)
MF available from INIS under the Report Number.Files
6165923.pdf
Files
(1.3 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 69 p.
- Report number
- ORNL-TM--4740
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 6165923
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Descriptors DEI
- AFTER-HEAT; COMPARATIVE EVALUATIONS; CONFIGURATION; DATA; DISTRIBUTION; HTGR TYPE REACTORS; LOSS OF FLOW; MATHEMATICAL MODELS; SCRAM; SPATIAL DISTRIBUTION; TRANSIENTS; VRAIN REACTOR
- Descriptors DEC
- ACCIDENTS; ENRICHED URANIUM REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; INFORMATION; POWER REACTORS; REACTOR ACCIDENTS; REACTOR SHUTDOWN; REACTORS
Optional Information
- Secondary number(s)
- CF--73-9-25.