MINET (Momentum Integral NETwork) analysis of MHTGR (Modular High Temperature Gas-Cooled Reactor) moisture-ingress transient
Conference
·
OSTI ID:5226339
The transient which involved a steam-generator tube leak and the ingress of moisture into the primary coolant system of the standard Modular Modular High Temperature Gas-Cooled Reactor (MHTGR) is analyzed by using the MINET (Momentum Integral NETwork) computer code. The analysis provides detailed information on the effect of power excursion on transient system pressures and temperatures. It is concluded that during the short term transient period the moisture ingress presents no threat to the integrity of the fuel elements and does not lead to pressures which would cause relief valve opening and fission product release.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5226339
- Report Number(s):
- BNL-NUREG-40364; CONF-880532-7; ON: DE88002126
- Resource Relation:
- Conference: American Nuclear Society topical meeting, Seattle, WA, USA, 1 May 1988
- Country of Publication:
- United States
- Language:
- English
Similar Records
The magnitude and reactivity consequences of accidental moisture ingress into the MHTGR core
Magnitude and reactivity consequences of accidental moisture ingress into the Modular High-Temperature Gas-Cooled Reactor core
Magnitude and reactivity consequences of accidental moisture ingress into the Modular High-Temperature Gas-Cooled Reactor core
Conference
·
Wed Jan 01 00:00:00 EST 1992
·
OSTI ID:5226339
Magnitude and reactivity consequences of accidental moisture ingress into the Modular High-Temperature Gas-Cooled Reactor core
Conference
·
Tue Dec 01 00:00:00 EST 1992
·
OSTI ID:5226339
Magnitude and reactivity consequences of accidental moisture ingress into the Modular High-Temperature Gas-Cooled Reactor core
Conference
·
Wed Jan 01 00:00:00 EST 1992
·
OSTI ID:5226339
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
HTGR TYPE REACTORS
STEAM GENERATORS
MOISTURE
M CODES
TUBES
LEAKS
AIR FLOW
FISSION PRODUCT RELEASE
FUEL ELEMENTS
HEAT TRANSFER
HYDRAULICS
PRESSURE EFFECTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
TEMPERATURE EFFECTS
TRANSIENTS
VALUES
BOILERS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
GAS COOLED REACTORS
GAS FLOW
GRAPHITE MODERATED REACTORS
MECHANICS
REACTOR COMPONENTS
REACTORS
SAFETY
VAPOR GENERATORS
220900* - Nuclear Reactor Technology- Reactor Safety
210300 - Power Reactors
Nonbreeding
Graphite Moderated
990220 - Computers
Computerized Models
& Computer Programs- (1987-1989)
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
HTGR TYPE REACTORS
STEAM GENERATORS
MOISTURE
M CODES
TUBES
LEAKS
AIR FLOW
FISSION PRODUCT RELEASE
FUEL ELEMENTS
HEAT TRANSFER
HYDRAULICS
PRESSURE EFFECTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
TEMPERATURE EFFECTS
TRANSIENTS
VALUES
BOILERS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
GAS COOLED REACTORS
GAS FLOW
GRAPHITE MODERATED REACTORS
MECHANICS
REACTOR COMPONENTS
REACTORS
SAFETY
VAPOR GENERATORS
220900* - Nuclear Reactor Technology- Reactor Safety
210300 - Power Reactors
Nonbreeding
Graphite Moderated
990220 - Computers
Computerized Models
& Computer Programs- (1987-1989)