PIUS reactor inherent shutdown following loss of feedwater

Conference · Wed Nov 01 00:00:00 EST 1989 · Transactions of the American Nuclear Society; (United States)

OSTI ID:5487598

Fredell, J ^[1]

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1. ABB Atom AB, Vaesteras (Sweden)

Employing the PIUS design principle, pressurized water reactors can be provided with unique characteristics that make their safety independent of conventional safety systems and virtually immune to human error during operation. A basic feature of this principle is the self-protective thermohydraulic design of the primary system, which prevents core power from exceeding the cooling capability of the submerging water, independent of outside surveillance and intervention. The principles of the PIUS reactor design are not repeated in this paper. This paper describes in detail one typical case illustrating the action of the self-protective thermohydraulics, namely, an unmonitored total loss of feedwater in the complete absence of safety system intervention (i.e., an anticipated transient without scram). The main coolant pumps are assumed to operate in the normal manner. The transient has been analyzed by the RIGEL code, which has been developed for the study of PIUS-type reactors.

• OSTI ID: 5487598
• Report Number(s): CONF-891103-; CODEN: TANSA; TRN: 91-024631
• Journal Information: Transactions of the American Nuclear Society; (United States), Vol. 60; Conference: Winter meeting of the American Nuclear Society (ANS) and nuclear power and technology exhibit, San Francisco, CA (United States), 26-30 Nov 1989; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ENGINEERED SAFETY SYSTEMS
PERFORMANCE
LOSS OF COOLANT
MITIGATION
PWR TYPE REACTORS
REACTOR SAFETY
AFTER-HEAT REMOVAL
ATWS
BORON
FEEDWATER
HEAT TRANSFER
HUMAN FACTORS
HYDRAULICS
PRIMARY COOLANT CIRCUITS
PUMPS
REACTIVITY
REACTOR CORES
REACTOR SHUTDOWN
STEAM GENERATORS
SURVEILLANCE
TRANSIENTS
ACCIDENTS
BOILERS
COOLING SYSTEMS
ELEMENTS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
HYDROGEN COMPOUNDS
MECHANICS
OXYGEN COMPOUNDS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
REMOVAL
SAFETY
SEMIMETALS
SHUTDOWN
VAPOR GENERATORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled