DETAILED ANALYSIS OF LOSS-OF-POWER ACCIDENT. HAZARDS ANALYSIS

Technical Report · Sun Mar 19 23:00:00 EST 1961

OSTI ID:4717438

Lampe, D A

The EGCR core coolant flow requirements following a loss-of-power accident were evaluated, and the conclusions reached in the preliminary anaiyses performed and reported in study IV-311 were examined. This evaluation is based upon analogue computer studies using the method outlined in an appendix to study IV-311. (auth)

• Research Organization: Allis-Chalmers Mfg. Co. Atomic Energy Div., Washington, D.C.
• NSA Number: NSA-17-022847
• OSTI ID: 4717438
• Report Number(s): ACNP-62606; EGCR-STUDY-IV-311-
• Country of Publication: United States
• Language: English

Related Subjects

ACCIDENTS
ANALOG SYSTEMS
COMPUTERS
COOLANT LOOPS
EGCR
FLUID FLOW
GAS COOLANT
LOSSES
POWER
POWER PLANTS
REACTOR CORE
REACTOR TECHNOLOGY