PARCH: a FORTRAN-IV digital program to evaluate pool boiling, axial rod and coolant heatup
Technical Report
·
OSTI ID:7100795
This report details changes made to C-E's ECCS version of the PARCH code resulting from a new NRC requirement concerning blowdown heat transfer. The report also documents some minor changes which were made to improve the code methodology. Sensitivity studies performed in order to determine the effects of the changes on peak clad temperature and clad oxidation are also documented in this report.
- Research Organization:
- Combustion Engineering, Inc., Windsor, CT (USA)
- OSTI ID:
- 7100795
- Report Number(s):
- CENPD-138(Suppl.2)
- Country of Publication:
- United States
- Language:
- English
Similar Records
CEFLASH-4A: a FORTRAN-IV digital computer program for reactor blowdown analysis. [PWR]
PARCH: a FORTRAN IV digital computer program to evaluate pool-boiling axial rod and coolant heatup
STRIKIN-II: a cylindrical geometry fuel rod heat transfer program (June 1976 modifications)
Technical Report
·
Thu Mar 31 23:00:00 EST 1977
·
OSTI ID:5010368
PARCH: a FORTRAN IV digital computer program to evaluate pool-boiling axial rod and coolant heatup
Technical Report
·
Thu Aug 01 00:00:00 EDT 1974
·
OSTI ID:4279140
STRIKIN-II: a cylindrical geometry fuel rod heat transfer program (June 1976 modifications)
Technical Report
·
Tue Jun 01 00:00:00 EDT 1976
·
OSTI ID:7353718
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
BLOWDOWN
BOILING
BWR TYPE REACTORS
COMPUTER CODES
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
GE STANDARD REACTOR
HEAT TRANSFER
LOSS OF COOLANT
P CODES
PHASE TRANSFORMATIONS
POOL BOILING
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTORS
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
BLOWDOWN
BOILING
BWR TYPE REACTORS
COMPUTER CODES
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
GE STANDARD REACTOR
HEAT TRANSFER
LOSS OF COOLANT
P CODES
PHASE TRANSFORMATIONS
POOL BOILING
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS