Quarterly progress report on reactor safety programs sponsored by the NRC Division of Reactor Safety Research for April--June 1975. IV. High-temperature gas-cooled reactor program
Technical Report
·
OSTI ID:4165248
Digital computer codes for simulating the dynamics of HTGR components and systems were developed further. Component simulations for use in the overall NSS simulation have been completed and are operational for the core, steam generator, and turbine-generator, and initial runs have been made with a coupled core-steam generator model. Component models were also completed for the Core Auxiliary Heat Exchanger (CAHE) and Core Auxiliary Cooling Tower (CACT). Work continued on implementing the RECA code on the ORNL IBM 360 computers. 6 references. (auth)
- Research Organization:
- Oak Ridge National Lab., Tenn. (USA)
- DOE Contract Number:
- W-7405-ENG-26
- NSA Number:
- NSA-33-006827
- OSTI ID:
- 4165248
- Report Number(s):
- ORNL-TM--5021(Vol.4)
- Country of Publication:
- United States
- Language:
- English
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*HTGR TYPE REACTORS-- REACTOR SAFETY
*REACTOR SAFETY-- RESEARCH PROGRAMS
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*REACTOR SAFETY-- RESEARCH PROGRAMS
220900* --Nuclear Reactor Technology--Reactor Safety
COMPUTER CODES
N77300 --Reactors--Power Reactors
Non-breeding
Graphite Moderated
N77900* --Reactors--Reactor Safety & Environmental Aspects
POWER DISTRIBUTION
REACTOR ACCIDENTS
SIMULATION
TEMPERATURE GRADIENTS