General features of advanced pressurized water reactors with improved fuel utilization
The main feature of an advanced pressurized water reactor (APWR) with improved fuel utilization is a plutonium-enriched tight lattice core integrated in an unchanged primary system of a common pressurized water reactor (PWR) power station. Neutron physical investigations demonstrate that conversion ratios in excess of 0.9 and final burnups of about 45,000 MWd/tHM are obtained with a reload enrichment of 7.5% fissile plutonium. The moderatorvoid coefficient is calculated to be negative. The high pressure drop of an APWR core is compensated for by a slightly reduced coolant flow rate. Despite the fact that calculated safety parameters such as void coefficient, critical heat flux margin, and emergency core cooling behavior have to be proven by experiments, the homogeneous concept of a high-converting PWR appears to be feasible.
- Research Organization:
- Technical University of Braunschweig Institute for Spaceflight Engineering and Reactor Technology Pockelsstrasse 14, Postfach der TU: 3329, 3300 Braunschweig
- OSTI ID:
- 6885273
- Journal Information:
- Nucl. Technol.; (United States), Vol. 59:2
- Country of Publication:
- United States
- Language:
- English
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BURNUP
REACTOR CORES
REACTOR LATTICES
DESIGN
CONVERSION RATIO
CRITICAL HEAT FLUX
ECCS
EFFICIENCY
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FLOW RATE
MODERATORS
NUCLEAR FUEL CONVERSION
PLUTONIUM
PRESSURE DROP
PRIMARY COOLANT CIRCUITS
REACTOR SAFETY
VOID COEFFICIENT
ACTINIDES
COOLING SYSTEMS
ELEMENTS
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
HEAT FLUX
ISOTOPE ENRICHED MATERIALS
MATERIALS
METALS
REACTIVITY COEFFICIENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTORS
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TRANSURANIUM ELEMENTS
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WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* - Power Reactors
Nonbreeding
Light-Water Moderated
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