Emergency Cooling System limits for the K-reactor heavy Mark 16B-31 charge
Technical Report
·
OSTI ID:6845795
Power limits must be prescribed for each SRP reactor charge so that the Emergency Cooling System (ECS) will prevent core damage from exceeding 1% during a postulated loss-of-coolant accident or loss-of-pumping accident. For specified low probability circumstances the core damage must not exceed 5%. ECS limits have been specified for the Mark 15 charge and for the C-reactor 504 assembly Mark 22 charge. A Technical Standard presently defines minimum ECS flow requirements for the standard Mark 16B-31 charge. This document prescribes ECS limits for the Mark 16B and Mark 31A assemblies in the K-reactor heavy Mark, 16B-31. 18 refs., 6 figs.
- Research Organization:
- Savannah River Lab., Aiken, SC (USA)
- DOE Contract Number:
- AC09-76SR00001
- OSTI ID:
- 6845795
- Report Number(s):
- DPST-84-912; ON: DE88013943
- Country of Publication:
- United States
- Language:
- English
Similar Records
Heavy Mark 16B-Mark 31 reactivity data for shutdown and ECS (Emergency Cooling System) analysis
Revised Emergency Cooling System LOCA (loss-of-coolant accidents) limits for PKL-reactor Mark 16B-31 charges
Subcycle-specific emergency cooling limits
Technical Report
·
Sun Nov 18 23:00:00 EST 1984
·
OSTI ID:7131308
Revised Emergency Cooling System LOCA (loss-of-coolant accidents) limits for PKL-reactor Mark 16B-31 charges
Technical Report
·
Thu Oct 02 00:00:00 EDT 1986
·
OSTI ID:6961164
Subcycle-specific emergency cooling limits
Technical Report
·
Sun Dec 07 23:00:00 EST 1986
·
OSTI ID:5528542
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COOLING SYSTEMS
DATA
ECCS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLOW RATE
FLUID MECHANICS
HEAT TRANSFER
HEAVY WATER MODERATED REACTORS
HYDRAULICS
INFORMATION
K REACTOR
LIMITING VALUES
LOSS OF COOLANT
MECHANICS
NUMERICAL DATA
PRODUCTION REACTORS
PUMPS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORE DISRUPTION
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
SPECIAL PRODUCTION REACTORS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220700 -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COOLING SYSTEMS
DATA
ECCS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLOW RATE
FLUID MECHANICS
HEAT TRANSFER
HEAVY WATER MODERATED REACTORS
HYDRAULICS
INFORMATION
K REACTOR
LIMITING VALUES
LOSS OF COOLANT
MECHANICS
NUMERICAL DATA
PRODUCTION REACTORS
PUMPS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORE DISRUPTION
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
SPECIAL PRODUCTION REACTORS