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Title: Relating surveillance capsule measurements to pressure vessel damage

Technical Report ·
DOI:https://doi.org/10.2172/5489185· OSTI ID:5489185

As part of the pressure vessel (PV) materials surveillance program, surveillance capsules including material specimens and neutron flux dosimeters are generally required to monitor changes in the fracture toughness properties of the reactor vessel materials. These capsules are withdrawn sequentially according to a predetermined schedule covering the service life of the vessel, and specimen material changes and dosimeter activation measured. The neutron fluence accumulated by the flux dosimeters is determined from the measured dosimeter activation and known reaction cross section (in practice, the /sup 54/Fe(n,p)/sup 54/Mn reaction.) The capsule fluence and material changes are then extrapolated to the pressure vessel using a fluence lead-factor determined from detailed multigroup neutron transport calculations. Typically, in this extrapolation changes in neutron spectrum are neglected. The purpose of this study is twofold; first, to determine the effect of including spectral changes in the extrapolation from capsule to vessel and second, to evaluate the effect of using the latest ENDF/B-V /sup 54/Fe(n,p)/sup 54/Mn cross sections in converting dosimeter activation to fluence.

Research Organization:
Brookhaven National Lab. (BNL), Upton, NY (United States)
DOE Contract Number:
EY-76-C-02-0016
OSTI ID:
5489185
Report Number(s):
BNL-NUREG-27192; CONF-800607-24; TRN: 80-008539
Resource Relation:
Conference: American Nuclear Society annual meeting, Las Vegas, NV, USA, 8 Jun 1980
Country of Publication:
United States
Language:
English