Transport analysis of several cross-section libraries used for reactor pressure vessel fluence calculations

Journal Article · Sun Jan 31 23:00:00 EST 1993 · Nuclear Technology; (United States)

OSTI ID:6757333

Haghighat, A; Veerasingam, R ^[1]

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1. The Pennsylvania State Univ., University Park (United States)

Several neutron cross-section libraries used for fluence calculations at the reactor pressure vessel (RPV) based on one-dimensional S[sub N] transport calculations are analyzed. It is demonstrated the BUGLE-80, SAILOR, and ELXSIR libraries yield similar results, while the CASK library predicts significantly different results through and beyond the RPV. The use of the revised ENDF/B-V iron cross sections yields a significant increase in the neutron fluxes beyond the iron-containing regions. This result has direct impact on the reactor cavity dosimetry that is being considered for the RPV fluence estimation.

• OSTI ID: 6757333
• Journal Information: Nuclear Technology; (United States), Journal Name: Nuclear Technology; (United States) Vol. 101:2; ISSN 0029-5450; ISSN NUTYBB
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
COMPARATIVE EVALUATIONS
CONTAINERS
CROSS SECTIONS
DOSIMETRY
EMBRITTLEMENT
EVALUATION
NEUTRAL-PARTICLE TRANSPORT
NEUTRON FLUENCE
NEUTRON FLUX
NEUTRON TRANSPORT
NUCLEAR DATA COLLECTIONS
PRESSURE VESSELS
RADIATION FLUX
RADIATION TRANSPORT
REACTORS