Quarterly progress report on high-temperature gas-cooled reactor safety studies sponsored by the NRC Division of Reactor Safety Research for October--December 1975
Research progress is briefly reported for the following tasks: reheater and steam generator model development, development of the nuclear steam supply system simulation code, core simulation for enemergency cooling analysis, core auxiliary cooling system model development, and computer code implementation.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- DOE Contract Number:
- W-7405-ENG-26
- NSA Number:
- NSA-33-032386
- OSTI ID:
- 4003286
- Report Number(s):
- ORNL/TM-5255
- Resource Relation:
- Other Information: Orig. Receipt Date: 30-JUN-76
- Country of Publication:
- United States
- Language:
- English
Similar Records
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
Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, October--December 1977
Quarterly progress report on the creepdown and collapse of Zircaloy fuel cladding program sponsored by the NRC Division of Reactor Safety Research for October--December 1975
Technical Report
·
Mon Sep 01 00:00:00 EDT 1975
·
OSTI ID:4003286
Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, October--December 1977
Technical Report
·
Sun Jan 01 00:00:00 EST 1978
·
OSTI ID:4003286
Quarterly progress report on the creepdown and collapse of Zircaloy fuel cladding program sponsored by the NRC Division of Reactor Safety Research for October--December 1975
Technical Report
·
Sun Feb 01 00:00:00 EST 1976
·
OSTI ID:4003286
Related Subjects
N77900* -Reactors-Reactor Safety & Environmental Aspects
N77300 -Reactors-Power Reactors
Non-breeding
Graphite Moderated
220900* -Nuclear Reactor Technology-Reactor Safety
*HTGR TYPE REACTORS- REACTOR SAFETY
*REACTOR SAFETY- RESEARCH PROGRAMS
COMPUTER CODES
FLUID FLOW
HEAT EXCHANGERS
HEAT TRANSFER
LOSS OF FLOW
STEAM GENERATORS
N77300 -Reactors-Power Reactors
Non-breeding
Graphite Moderated
220900* -Nuclear Reactor Technology-Reactor Safety
*HTGR TYPE REACTORS- REACTOR SAFETY
*REACTOR SAFETY- RESEARCH PROGRAMS
COMPUTER CODES
FLUID FLOW
HEAT EXCHANGERS
HEAT TRANSFER
LOSS OF FLOW
STEAM GENERATORS