High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research. Quarterly progress report, January 1, 1977--March 31, 1977

Technical Report · Tue May 31 00:00:00 EDT 1977

OSTI ID:7105181

Ball, S J; Cleveland, J C; Conklin, J C; Sanders, J P

Work on HTGR safety studies this quarter was primarily on refining the ORTAP code for the Fort St. Vrain Reactor to cover wider operating ranges. General Atomic Company's TAP program was implemented on the IBM 360 system at ORNL.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26; NRC-INA-40-551-75
• OSTI ID: 7105181
• Report Number(s): ORNL/NUREG/TM-115
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HTGR TYPE REACTORS
REACTOR SAFETY
RESEARCH PROGRAMS
VRAIN REACTOR
TRANSIENTS
COMPUTER CODES
DEPRESSURIZATION
HEAT TRANSFER
O CODES
STEAM GENERATORS
BOILERS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
POWER REACTORS
REACTORS
SAFETY
VAPOR GENERATORS
220900* - Nuclear Reactor Technology- Reactor Safety
210300 - Power Reactors
Nonbreeding
Graphite Moderated