A HYBRID-COMPUTER PROGRAM FOR TRANSIENT TEMPERATURE CALCULATIONS ON TREAT FAST REACTOR SAFETY EXPERIMENTS.

Technical Report · Sun Jan 01 00:00:00 EST 1967

DOI:https://doi.org/10.2172/4559840· OSTI ID:4559840

Bryant, L T; Amiot, L W; Dickerman, C E; Stephany, W P

• Research Organization: Argonne National Lab., Ill.
• Sponsoring Organization: USDOE
• DOE Contract Number: W-31-109-ENG-38
• NSA Number: NSA-22-014122
• OSTI ID: 4559840
• Report Number(s): ANL-7374
• Resource Relation: Other Information: UNCL. Orig. Receipt Date: 31-DEC-68
• Country of Publication: United States
• Language: English

Related Subjects

N38180* -Power Reactor Development-Safety & Siting
ANALOG SYSTEMS
DETERMINATION
DIGITAL SYSTEMS
FAST NEUTRONS
PROGRAMMING
REACTOR SAFETY
REACTORS
RESEARCH REACTORS
TEMPERATURE
TRANSIENTS
TREAT
USES
REACTORS
FAST/temperature calculations for TREAT
analog-digital computer program for transient
REACTOR SAFETY EXPERIMENTS/ temperature calculations for TREAT
analog-digital computer program for transient