Published January 3, 1977
| Version v1
Report
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Summary progress report for fiscal year 1976 and the transition quarter describing technical assistance work for the Division of Systems Safety, U.S. Nuclear Regulatory Commission
Description
The report reviews briefly the HTGR core analytical methods that were developed during the course of the program. The features of these analytical methods are compared with methods used to perform similar analyses, and examples of the use of these methods are cited. Included are discussions of HEATUP (a computer code for the thermal analysis of an LOFC accident in an HTGR), HEATING 5 (an IBM 360 heat-conduction code), CCCM (a coupled conduction-convection model for core thermal analysis), FLODIS (a computer model to determine the flow distribution and thermal response of the Vrain reactor), and HEXEREI 2 code development
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS. $4.00.Files
8324884.pdf
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Additional details
Additional titles
- Augmented title (English)
- HTGR
Publishing Information
- Imprint Pagination
- 46 p.
- Report number
- ORNL/NUREG--6
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8324884
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Progress Report
- Descriptors DEI
- COMPUTER CALCULATIONS; COMPUTER CODES; F CODES; H CODES; HEAT TRANSFER; HTGR TYPE REACTORS; LOSS OF FLOW; MATHEMATICAL MODELS; REACTOR SAFETY; RESEARCH PROGRAMS
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY