Experimental estimation of neutron fluxes from niobium impurities in the pressure vessel steel of nuclear power reactors

Bruno Bärs, Erkki Häsänen

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3 Citations (Scopus)

Abstract

Nb impurities in samples from radioactive pressure vessel material have been chemically separated and purified twice by liquid ion exchange chromatography. The 93mNb activity from the fast neutron induced reaction 93Nb(n, n′)93mNb was measured by liquid scintillation counting (LSC). The remaining interference from 54Mn in the LSC spectra was subtracted based on LSC spectra from pure 54Mn.
The corresponding Nb masses in the purified solutions were measured with an inductively coupled plasma mass spectrometer (ICP-MS). The specific activity of 93mNb in the pressure vessel material studied was 5–30 Bq/μg Nb and was further used to estimate the corresponding reaction rates, neutron fluxes and doses. Due to the long half-life (16.1 yr) and low threshold energy (about 1 MeV) Nb is an excellent dosimeter material.
Since steel with Nb impurities is a common construction material e.g. the 54Mn(n,p)54Mn (312.2 d, about 3 MeV) and 93Nb(n, n′)93mNb reactions can be used to experimentally estimate the neutron doses and check some shape index for the neutron spectra in radioactive samples from pressure vessels and reactor structure materials.
This work is a novel application of Nb for dosimetric purposes.
Original languageEnglish
Pages (from-to)577-580
JournalNuclear Instruments and Methods in Physics Research. Section A: Accelerators, Spectrometers, Detectors and Associated Equipment
Volume317
Issue number3
DOIs
Publication statusPublished - 1992
MoE publication typeA1 Journal article-refereed

Fingerprint

nuclear power reactors
pressure vessels
Neutron flux
Steel structures
flux (rate)
Niobium
niobium
Nuclear energy
Scintillation
Pressure vessels
steels
Impurities
scintillation
impurities
counting
Neutrons
Liquids
liquids
dosage
Dosimeters

Keywords

  • nuclear reactors

Cite this

@article{f1ef3eee6c904b9fa91ef3f5a8aa3457,
title = "Experimental estimation of neutron fluxes from niobium impurities in the pressure vessel steel of nuclear power reactors",
abstract = "Nb impurities in samples from radioactive pressure vessel material have been chemically separated and purified twice by liquid ion exchange chromatography. The 93mNb activity from the fast neutron induced reaction 93Nb(n, n′)93mNb was measured by liquid scintillation counting (LSC). The remaining interference from 54Mn in the LSC spectra was subtracted based on LSC spectra from pure 54Mn. The corresponding Nb masses in the purified solutions were measured with an inductively coupled plasma mass spectrometer (ICP-MS). The specific activity of 93mNb in the pressure vessel material studied was 5–30 Bq/μg Nb and was further used to estimate the corresponding reaction rates, neutron fluxes and doses. Due to the long half-life (16.1 yr) and low threshold energy (about 1 MeV) Nb is an excellent dosimeter material. Since steel with Nb impurities is a common construction material e.g. the 54Mn(n,p)54Mn (312.2 d, about 3 MeV) and 93Nb(n, n′)93mNb reactions can be used to experimentally estimate the neutron doses and check some shape index for the neutron spectra in radioactive samples from pressure vessels and reactor structure materials. This work is a novel application of Nb for dosimetric purposes.",
keywords = "nuclear reactors",
author = "Bruno B{\"a}rs and Erkki H{\"a}s{\"a}nen",
note = "Project code: met00134",
year = "1992",
doi = "10.1016/0168-9002(92)91004-S",
language = "English",
volume = "317",
pages = "577--580",
journal = "Nuclear Instruments and Methods in Physics Research. Section A: Accelerators, Spectrometers, Detectors and Associated Equipment",
issn = "0168-9002",
publisher = "Elsevier",
number = "3",

}

TY - JOUR

T1 - Experimental estimation of neutron fluxes from niobium impurities in the pressure vessel steel of nuclear power reactors

AU - Bärs, Bruno

AU - Häsänen, Erkki

N1 - Project code: met00134

PY - 1992

Y1 - 1992

N2 - Nb impurities in samples from radioactive pressure vessel material have been chemically separated and purified twice by liquid ion exchange chromatography. The 93mNb activity from the fast neutron induced reaction 93Nb(n, n′)93mNb was measured by liquid scintillation counting (LSC). The remaining interference from 54Mn in the LSC spectra was subtracted based on LSC spectra from pure 54Mn. The corresponding Nb masses in the purified solutions were measured with an inductively coupled plasma mass spectrometer (ICP-MS). The specific activity of 93mNb in the pressure vessel material studied was 5–30 Bq/μg Nb and was further used to estimate the corresponding reaction rates, neutron fluxes and doses. Due to the long half-life (16.1 yr) and low threshold energy (about 1 MeV) Nb is an excellent dosimeter material. Since steel with Nb impurities is a common construction material e.g. the 54Mn(n,p)54Mn (312.2 d, about 3 MeV) and 93Nb(n, n′)93mNb reactions can be used to experimentally estimate the neutron doses and check some shape index for the neutron spectra in radioactive samples from pressure vessels and reactor structure materials. This work is a novel application of Nb for dosimetric purposes.

AB - Nb impurities in samples from radioactive pressure vessel material have been chemically separated and purified twice by liquid ion exchange chromatography. The 93mNb activity from the fast neutron induced reaction 93Nb(n, n′)93mNb was measured by liquid scintillation counting (LSC). The remaining interference from 54Mn in the LSC spectra was subtracted based on LSC spectra from pure 54Mn. The corresponding Nb masses in the purified solutions were measured with an inductively coupled plasma mass spectrometer (ICP-MS). The specific activity of 93mNb in the pressure vessel material studied was 5–30 Bq/μg Nb and was further used to estimate the corresponding reaction rates, neutron fluxes and doses. Due to the long half-life (16.1 yr) and low threshold energy (about 1 MeV) Nb is an excellent dosimeter material. Since steel with Nb impurities is a common construction material e.g. the 54Mn(n,p)54Mn (312.2 d, about 3 MeV) and 93Nb(n, n′)93mNb reactions can be used to experimentally estimate the neutron doses and check some shape index for the neutron spectra in radioactive samples from pressure vessels and reactor structure materials. This work is a novel application of Nb for dosimetric purposes.

KW - nuclear reactors

U2 - 10.1016/0168-9002(92)91004-S

DO - 10.1016/0168-9002(92)91004-S

M3 - Article

VL - 317

SP - 577

EP - 580

JO - Nuclear Instruments and Methods in Physics Research. Section A: Accelerators, Spectrometers, Detectors and Associated Equipment

JF - Nuclear Instruments and Methods in Physics Research. Section A: Accelerators, Spectrometers, Detectors and Associated Equipment

SN - 0168-9002

IS - 3

ER -