Vessel fluence assessment with EFLUVE and low-fluence fuel management

Conference · Tue Jan 01 04:00:00 EST 1991 · Transactions of the American Nuclear Society; (United States)

OSTI ID:5778958

Rosset, F D; Schaeffer, H ^[1]; Leroy, P ^[2]

---

1. Electricite de France, Clamart (France)
2. Electricite de France, Paris (France)

A software package enabling simple, quick assessment of pressurized water reactor (PWR) vessel fluence is described. The incidence of low-fluence loading patterns on vessel fluence is then discussed in the context of mixed-oxide (MOX) fuel management. Electricite de France (EdF) decided to develop simple tools to assess fluence in the vessel base metal or even in the surveillance program capsules on the basis of core fission sources. EFLUVE (Evaluation of FLUence in the VEssel) 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 neutrons > 1 MeV received on the vessel or the capsules and then calculate their fluence. Calculation result comparisons were performed with EFLUVE and the French reference code TRIPOLI 2 (which uses the three-dimensional Monte Carlo resolution method) on standard 900-MW (electric) PWR fuel management (three-batch UO{sub 2} 3.25%) and also on other fuel managements as four-batch UO{sub 2}/three-batch MOX fuel.

• OSTI ID: 5778958
• Report Number(s): CONF-910603--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 63
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ACTINIDE COMPOUNDS
BARYONS
CHALCOGENIDES
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTAINERS
DEVELOPED COUNTRIES
E CODES
ELEMENTARY PARTICLES
ENRICHED URANIUM REACTORS
EUROPE
FAST NEUTRONS
FERMIONS
FISSION
FRANCE
FUEL ASSEMBLIES
FUEL MANAGEMENT
FUELS
HADRONS
MIXED OXIDE FUELS
NEUTRON FLUENCE
NEUTRON LEAKAGE
NEUTRONS
NUCLEAR REACTIONS
NUCLEONS
OPERATION
OXIDES
OXYGEN COMPOUNDS
POWER REACTORS
PRESSURE VESSELS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTOR FUELING
REACTOR OPERATION
REACTOR SAFETY
REACTORS
SAFETY
SIMULATION
SOLID FUELS
THERMAL REACTORS
THREE-DIMENSIONAL CALCULATIONS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS