RELAP4/MOD6; transient thermal-hydraulic study. [IBM360,370; CDC7600; FORTRAN IV (95) and BAL (5) (IBM360), FORTRAN IV (95) and COMPASS (5) (CDC7600)]
RELAP4 has been developed to describe the behavior of water-cooled nuclear reactors subjected to postulated transients, such as those resulting from loss-of-coolant, pump failure, or power excursions. The program calculates fluid conditions such as flow, pressure, mass inventory, and quality; thermal conditions such as surface temperatures, temperature profiles, and energy distributions; and heat fluxes in power generating and dissipating elements. The program also calculates reactor power, decay heat, and reactivity. In addition to describing transients in boiling-water and pressurized-water reactors, the program is sufficiently versatile to describe transients in experimental thermal-hydraulic systems. RELAP4/MOD6 was developed specifically to add a capability to the earlier RELAP codes for calculating PWR reflood phenomena.IBM360,370;CDC7600; FORTRAN IV (95%) and BAL (5%) (IBM360), FORTRAN IV (95%) and COMPASS (5%) (CDC7600); OS/360,370 (IBM360,370), SCOPE (CDC7600); 850K bytes (IBM360), 160,000 (octal) words of SCM and 200,000 (octal) words of LCM (CDC7600), 3 tape drives, and a CalComp plotter.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- OSTI ID:
- 6344516
- Report Number(s):
- ANL/NESC-369; ON: DE83048369
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ACCIDENTS
BLOWDOWN
BWR TYPE REACTORS
COMPUTER CODES
ENERGY TRANSFER
EXCURSIONS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
HYDRODYNAMICS
MECHANICS
POWER PLANTS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
THERMODYNAMICS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS