High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research. Quarterly progress report, October 1, 1976--December 31, 1976
Technical Report
·
OSTI ID:7311008
Work on HTGR safety studies during the reporting period was aimed primarily at expanding the capabilities of the ORTAP code to cover post turbine trip periods and low- or zero-flow situations in the core. The implementation of the TAP program on the IBM 360 system at ORNL is continuing. The IBM 360 versions of the POKE and OXIDE-3 programs will be transmitted to BNL for permanent storage.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 7311008
- Report Number(s):
- ORNL/NUREG/TM-96
- Country of Publication:
- United States
- Language:
- English
Similar Records
High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research. Quarterly progress report, January 1, 1977--March 31, 1977
High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research. Quarterly progress report, April 1--June 30, 1977
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
·
Tue May 31 00:00:00 EDT 1977
·
OSTI ID:7105181
High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research. Quarterly progress report, April 1--June 30, 1977
Technical Report
·
Tue Sep 20 00:00:00 EDT 1977
·
OSTI ID:7295759
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
·
Mon Sep 01 00:00:00 EDT 1975
·
OSTI ID:4165248
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BOILERS
COMPUTER CALCULATIONS
COMPUTER CODES
DEPRESSURIZATION
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HEAT TRANSFER
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
O CODES
POWER REACTORS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
STEAM GENERATORS
TRANSIENTS
VAPOR GENERATORS
VRAIN REACTOR
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BOILERS
COMPUTER CALCULATIONS
COMPUTER CODES
DEPRESSURIZATION
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HEAT TRANSFER
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
O CODES
POWER REACTORS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
STEAM GENERATORS
TRANSIENTS
VAPOR GENERATORS
VRAIN REACTOR