Published January 3, 1977 | Version v1
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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.

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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