Benchmarking of pressure vessel fluence calculations

Conference · Sun Jan 01 04:00:00 EST 1984

OSTI ID:6862634

Cokinos, D M; Carew, J F; Kohut, P; Todosow, M

Extended neutron irradiation of certain PWR pressure vessels (PVs) causing significant degradation of vessel material mechanical and structural properties, coupled with the concern that in a PWR transient the pressure vessel may be subjected to pressurized thermal shock, has resulted in a need for accurate and well benchmarked calculations of accumulated pressure vessel fluence. This paper presents results of pressure vessel fluence benchmark calculations and comparisons with measurement data, performed as part of the BNL/NRC Pressure Vessel Embrittlement program. The benchmarking effort consisted of calculations of the fast (>1-MeV) neutron fluence for (1) the PV surveillance capsules of two Combustion Engineering reactors (CE-1, a 217-assembly plant, and CE-2, a 133-assembly plant) and a 177-assembly Babcock and Wilcox reactor (B and W-1), (2) flux measurements made in the cavity of a 177-assembly B and W reactor (B and W-2) and (3) the ORNL/PCA benchmark experiment.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 6862634
• Report Number(s): BNL-NUREG-34244; CONF-840614-42; ON: DE84007375
• 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
ALLOYS
BENCHMARKS
CONTAINERS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
NEUTRON FLUX
PRESSURE VESSELS
PWR TYPE REACTORS
RADIATION FLUX
REACTOR MATERIALS
REACTORS
STEELS
WATER COOLED REACTORS
WATER MODERATED REACTORS