Impact of the ENDF/B-VI cross sections on the RPV fluence determination

I. Remec

doi:10.1520/stp13588s

Impact of the ENDF/B-VI cross sections on the RPV fluence determination

I. Remec

STS Project Technical Systems

Research output: Contribution to journal › Conference article › peer-review

Abstract

The calculations with the broad-group cross-section library Bugle-96, and atom displacement (dpa) cross sections for iron, both derived from ENDF/B-VI data, result in higher calculated fast neutron fluxes, better agreement of calculations with radiometric dosimeter measurements, and significantly slower dpa rate attenuation through pressure vessel walls relative to the results with their predecessors: the Sailor library and ASTM iron dpa cross sections.

Original language	English
Pages (from-to)	124-131
Number of pages	8
Journal	ASTM Special Technical Publication
Issue number	1398
DOIs	https://doi.org/10.1520/stp13588s
State	Published - 2001
Event	Reactor Dosimetry: Radiation Metrology and Assesment - Osaka, Japan Duration: Sep 12 1999 → Sep 17 1999

Keywords

Dosimetry
ENDF/B-VI
Neutron transport
Reactor pressure vessel

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10.1520/stp13588s

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title = "Impact of the ENDF/B-VI cross sections on the RPV fluence determination",

abstract = "The calculations with the broad-group cross-section library Bugle-96, and atom displacement (dpa) cross sections for iron, both derived from ENDF/B-VI data, result in higher calculated fast neutron fluxes, better agreement of calculations with radiometric dosimeter measurements, and significantly slower dpa rate attenuation through pressure vessel walls relative to the results with their predecessors: the Sailor library and ASTM iron dpa cross sections.",

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journal = "ASTM Special Technical Publication",

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AU - Remec, I.

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AB - The calculations with the broad-group cross-section library Bugle-96, and atom displacement (dpa) cross sections for iron, both derived from ENDF/B-VI data, result in higher calculated fast neutron fluxes, better agreement of calculations with radiometric dosimeter measurements, and significantly slower dpa rate attenuation through pressure vessel walls relative to the results with their predecessors: the Sailor library and ASTM iron dpa cross sections.

KW - Dosimetry

KW - ENDF/B-VI

KW - Neutron transport

KW - Reactor pressure vessel

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DO - 10.1520/stp13588s

M3 - Conference article

AN - SCOPUS:0035555075

SN - 0066-0558

SP - 124

EP - 131

JO - ASTM Special Technical Publication

JF - ASTM Special Technical Publication

IS - 1398

T2 - Reactor Dosimetry: Radiation Metrology and Assesment

Y2 - 12 September 1999 through 17 September 1999

ER -

Impact of the ENDF/B-VI cross sections on the RPV fluence determination

Abstract

Keywords

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