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Title: PWR (pressurized water reactor) pressure vessel neutron spectra at McGuire-1: Final report

Technical Report ·
OSTI ID:5655723

Neutron energy spectra for the McGuire-1 reactor, a PWR designed by Westinghouse and owned and operated by the Duke Power Co., have been calculated using the transport codes XSDRNPM, ANISN, and DOT-4.2. This is the third report of a series, the other two being reports containing similar information for the Arkansas Power and Light reactors ANO-1 and ANO-2. The objective of this effort is the establishment of a benchmark methodology for the most accurate computation of the fast neutron fluence hitting the Pressure Vessel of a PWR. To perform the calculations, a R-theta model of McGuire-1 was established for the 2-D transport code DOT-4.2. The R-theta neutron flux thus obtained formed the basis for a 3-D flux synthesized with the help of a ''leakage factor'' which was calculated, group by group, from a R-Z DOT flux and an ANISN 1-D flux. This 3-D flux was subsequently used to calculate reaction rates for several threshold foils irradiated in in-vessel and ex-vessel positions. The calculated reaction rates were compared with measured ones, when experimental data existed. Displacements per atom were also computed for several locations. As it was shown previously for ANO-1 and ANO-2, there is considerable angular variation of the flux hitting the pressure vessel. For McGuire-1, the steel pads that have been placed outside the core barrel, reduce the peak of the fast neutron flux but also move the peak from 45/sup 0/ to about 20/sup 0/, with respect to the flat of the core which is taken as the 0/sup 0/ direction.

Research Organization:
Missouri Univ., Rolla (USA). Dept. of Nuclear Engineering
OSTI ID:
5655723
Report Number(s):
EPRI-NP-5622; ON: TI88920213
Resource Relation:
Other Information: Includes 1 sheet of 24x reduction microfiche
Country of Publication:
United States
Language:
English