TRAC-P1A analysis of standard problem. [PWR]
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5284509
None
- Research Organization:
- Los Alamos Scientific Lab., NM
- OSTI ID:
- 5284509
- Report Number(s):
- CONF-791103-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 33
- Country of Publication:
- United States
- Language:
- English
Similar Records
TRAC-P1A calculations of Edwards' blowdown experiment. [PWR; BWR]
TRAC-P1 post-test analysis of U. S. standard problem. [PWR]
Independent assessment of TRAC-P1A with Moby-Dick nitrogen-water tests. [PWR]
Conference
·
Fri Jun 01 00:00:00 EDT 1979
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5855370
TRAC-P1 post-test analysis of U. S. standard problem. [PWR]
Conference
·
Sat Dec 31 23:00:00 EST 1977
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6432646
Independent assessment of TRAC-P1A with Moby-Dick nitrogen-water tests. [PWR]
Conference
·
Mon Dec 31 23:00:00 EST 1979
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6877344
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CALCULATIONS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CALCULATIONS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS