Vessel fluence assessment with the EFLUVE code and a low-fluence fuel management scheme
- Electricite de France, Clamart (France). Depart. Physique des Reacteurs
The EFLUVE software package enables simple and quick assessment of pressurized water reactor (PWR) vessel fluence. It is a three-dimensional code that analyzes neutron propagation inside and then outside the core by applying the straight-line attenuation method and using only fast neutrons. The code is designed to assess the flux of > 1-MeV neutrons received on the vessel or irradiation capsules and then to calculate their fluence. The purposes of this code are as follows: (1) to perform fast and sufficiently accurate calculations to enable continuous monitoring of the fluence in all PWR vessels, for all operating cycles, throughout the lifetime of all French PWRs (2) to provide a basis for parametric studies aimed at assessing the effect on fluence values of a new fuel management method [four-cycle UO[sub 2] or three-cycle mixed-oxide (MOX) fuel] (3) to assess the effect of plutonium in MOX fuel management. The effect of low-fluence loading patterns on vessel fluence is then discussed in the context of MOX fuel management. A vessel fluence reduction of [approximately]40% can be achieved for uranium and plutonium fuel management schemes with low-leakage loading patterns.
- OSTI ID:
- 7369047
- Journal Information:
- Nuclear Technology; (United States), Vol. 103:1; ISSN 0029-5450
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
PWR TYPE REACTORS
E CODES
FUEL MANAGEMENT
NEUTRON FLUENCE
FAST NEUTRONS
IRRADIATION CAPSULES
MIXED CARBIDE FUELS
NEUTRON TRANSPORT
NUCLEAR FUELS
PARAMETRIC ANALYSIS
PLUTONIUM
REACTOR CORES
REACTOR VESSELS
URANIUM DIOXIDE
ACTINIDE COMPOUNDS
ACTINIDES
BARYONS
CHALCOGENIDES
COMPUTER CODES
CONTAINERS
ELEMENTARY PARTICLES
ELEMENTS
ENERGY SOURCES
ENRICHED URANIUM REACTORS
FERMIONS
FUELS
HADRONS
MATERIALS
METALS
NEUTRAL-PARTICLE TRANSPORT
NEUTRONS
NUCLEONS
OXIDES
OXYGEN COMPOUNDS
POWER REACTORS
RADIATION TRANSPORT
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
THERMAL REACTORS
TRANSURANIUM ELEMENTS
URANIUM COMPOUNDS
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled