Core design and control of a soluble-boron-free passive PWR (pressurized water reactor)

Conference · Fri Jun 01 04:00:00 EDT 1990 · Transactions of the American Nuclear Society; (USA)

OSTI ID:6022166

Crump, M W; Kantrowitz, M L; Rudek, T G

The elimination of soluble boron from the primary coolant and safety systems is a major potential simplification for a passive pressurized water reactor (PWR), i.e., one which relies primarily on passive means for all essential safety functions. Soluble-boron-free (SBF) operation offers the significant advantages of (a) elimination of boric acid processing systems and the associated operational and maintenance requirements, (b) elimination of concerns related to boric-acid-induced corrosion on primary pressure boundary and plant components, and (c) presence of a strong negative moderator temperature coefficient (MTC) over the entire fuel cycle. In general, SBF operation impacts PWR design by increasing the control rod requirements, requiring greater use of burnable poisons, and increasing the core power peaking. Previous investigation has shown that SBF operation is feasible for a new PWR design based entirely on existing technology. That investigation considered the capability to provide adequate shutdown margin for cold conditions using only control rods, and to control the core reactivity and core power distribution over cycle using existing fuel and burnable poison designs. The work reported here builds on that effort by applying the SBF concept to a small, passive PWR core that satisfies the basic requirements of the Electric Power Research institute Advanced Light Water Reactor Passive Plant Program. Within the passive PWR framework, the evaluation addresses the impact of the SBF feature on core design, reactor control, and reactor safety.

• OSTI ID: 6022166
• Report Number(s): CONF-900608--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 61
• Country of Publication: United States
• Language: English

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22 GENERAL STUDIES OF NUCLEAR REACTORS
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BLACKOUTS
BORON
CONTROL ELEMENTS
CONTROL SYSTEMS
COOLING SYSTEMS
ELEMENTS
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
KINETICS
MAINTENANCE
MATERIALS
NUCLEAR POISONS
POWER DISTRIBUTION
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR KINETICS
REACTOR MAINTENANCE
REACTOR MATERIALS
REACTOR SAFETY
REACTORS
SAFETY
SECONDARY COOLANT CIRCUITS
SEMIMETALS
SOLUBLE POISONS
WATER COOLED REACTORS
WATER MODERATED REACTORS