MARCH1. 1; lwr meltdown accident response model. [CDC CYBER74,73,175; CDC6500; FORTRAN IV (92%) and COMPASS (8%). MARCH1. 1 was developed using CDC FORTRAN Extended]

Technical Report ·

OSTI ID:6460525

Wooton, R O

MARCH1.1 calculates primary system and containment response to small or large pipe breaks and transient accidents, which when combined with failure of engineered safety features can lead to core meltdown in water cooled reactors.CDC CYBER74,73,175;CDC6500; FORTRAN IV (92%) and COMPASS (8%). MARCH1.1 was developed using CDC FORTRAN Extended.; NOS/BE 1.4 (CDC CYBER74) and NOS 1.3 (CDC CYBER175); MARCH1.1 requires approximately 215K (octal) words of memory for execution.

• Research Organization: Battelle Columbus Labs., OH (USA)
• OSTI ID: 6460525
• Report Number(s): ANL/NESC-734; ON: DE83048734
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BLOWDOWN
COMPUTER CODES
CONTAINMENT
CONTAINMENT SYSTEMS
ENGINEERED SAFETY SYSTEMS
M CODES
MELTDOWN
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTORS
TRANSIENTS
WATER COOLED REACTORS