Revised decay heat tables for Mark 16B, Mark 22 and Mark 31 assemblies for use in ECS (Emergency Cooling System) analyses
Technical Report
·
OSTI ID:6961225
This report provides documentation of current calculations of the decay heats. These decay heats were obtained with procedures which will support a quality assurance audit of ECS analyses. The decay heat tables have also been extended to longer cooling times to support ECS analyses of potential interest to the Probabilistic Risk Assessment (PRA) program. These tables will allow calculations of the heat deposited in Mark 16B, Mark 22, Mark 31A, and Mark 31B assemblies by the processes of fission product decay in LOCA (loss-of-coolant-accident) and LOPA (loss-of-pumping-accident) scenarios. The theory and procedures for such assembly deposited power calculations are given in reference 6.
- Research Organization:
- Savannah River Lab., Aiken, SC (USA)
- DOE Contract Number:
- AC09-76SR00001
- OSTI ID:
- 6961225
- Report Number(s):
- DPST-85-828-Del.Ver.; ON: DE88013945
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220700* -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900 -- Nuclear Reactor Technology-- Reactor Safety
AFTER-HEAT
AFTER-HEAT REMOVAL
COMPUTER CODES
COOLING SYSTEMS
DATA
ECCS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
EQUATIONS
FLUID MECHANICS
FUEL ASSEMBLIES
H CODES
HEAT TRANSFER
HYDRAULICS
INFORMATION
MECHANICS
NATIONAL ORGANIZATIONS
NUMERICAL DATA
PRODUCTION REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
REMOVAL
RISK ASSESSMENT
SAFETY
SAVANNAH RIVER PLANT
SHIELDING
US AEC
US DOE
US ERDA
US ORGANIZATIONS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220700* -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900 -- Nuclear Reactor Technology-- Reactor Safety
AFTER-HEAT
AFTER-HEAT REMOVAL
COMPUTER CODES
COOLING SYSTEMS
DATA
ECCS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
EQUATIONS
FLUID MECHANICS
FUEL ASSEMBLIES
H CODES
HEAT TRANSFER
HYDRAULICS
INFORMATION
MECHANICS
NATIONAL ORGANIZATIONS
NUMERICAL DATA
PRODUCTION REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
REMOVAL
RISK ASSESSMENT
SAFETY
SAVANNAH RIVER PLANT
SHIELDING
US AEC
US DOE
US ERDA
US ORGANIZATIONS