Magnitude and reactivity consequences of moisture ingress into the modular High-Temperature Gas-Cooled Reactor core
- Oak Ridge National Lab., TN (United States)
Inadvertent admission of moisture into the primary system of a modular high-temperature gas-cooled reactor has been identified in US Department of Energy-sponsored studies as an important safety concern. The work described here develops an analytical methodology to quantify the pressure and reactivity consequences of steam-generator tube rupture and other moisture-ingress-related incidents. Important neutronic and thermohydraulic processes are coupled with reactivity feedback and safety and control system responses. The rate and magnitude of steam buildup are found to be dominated by major system features such as break size compared with safety valve capacity and reliability and less sensitive to factors such as heat transfer coefficients. The results indicate that ingress transients progress at a slower pace than previously predicted by bounding analyses, with milder power overshoots and more time for operator or automatic corrective actions.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; Oak Ridge National Lab., TN (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 10121046
- Report Number(s):
- NUREG/CR-5947; ORNL/TM-12237; ON: TI93005790
- Resource Relation:
- Other Information: PBD: Dec 1992
- Country of Publication:
- United States
- Language:
- English
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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
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HTGR TYPE REACTORS
REACTOR KINETICS
STEAM GENERATORS
FAILURES
REACTIVITY
MOISTURE
STEAM
MATHEMATICAL MODELS
TUBES
TRANSIENTS
ATWS
REACTOR SAFETY
REACTOR CONTROL SYSTEMS
HEAT TRANSFER
THERMODYNAMICS
220900
210300
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POWER REACTORS
NONBREEDING
GRAPHITE MODERATED
CONTROL SYSTEMS