Chemical methods for the use of niobium from pressure vessel cladding as a fast neutron dosimeter

Hari Karnani

Research output: Book/ReportReportProfessional

Abstract

The steel samples from the cladding of a pressure vessel of an operating nuclear power reactor were obtained by scraping. The cladding material of the pressure vessel contained about 0.5 % niobium. It was desired to use the niobium as a dosimeter for estimating fast fluences at the pressure vessel. The weak radiation from the reaction product 93mNb cannot be measured in the presence of other elements and interfering activities. A method was developed to separate niobium from other metals present; the concentration and yield of niobium were determined spectrophotometrically. The irradiated niobium was electrodeposited from aqueous solutions on copper discs. The amount of the deposited niobium was determined by a radiochemical method which makes use of its own radioactivity - measured with a liquid scintillation counter - and the known starting mass of niobium. It was possible to determine the deposited niobium masses (5 to 200 microgram) with a desired degree of accuracy. The absolute emission rate of X-rays could then be measured without any self-absorption or interference from other activities. The mass of niobium on each preparate and its X-ray emission rate, later on, were used as basic experimental data for the estimation of last neutron doses at the pressure vessel.
Original languageEnglish
Place of PublicationEspoo
PublisherVTT Technical Research Centre of Finland
Number of pages44
ISBN (Print)951-38-2600-7
Publication statusPublished - 1986
MoE publication typeD4 Published development or research report or study

Publication series

NameTiedotteita / Valtion teknillinen tutkimuskeskus
PublisherVTT
Volume605

Fingerprint

pressure vessels
fast neutrons
niobium
dosimeters
nuclear power reactors
self absorption
radioactivity
reaction products
scintillation counters
fluence
x rays
estimating
steels
aqueous solutions
interference
neutrons
copper
dosage

Keywords

  • nuclear reactors
  • fast neutrons
  • fluence
  • niobium
  • electrodeposition
  • pressure vessels
  • liquid scintilation counting

Cite this

Karnani, H. (1986). Chemical methods for the use of niobium from pressure vessel cladding as a fast neutron dosimeter. Espoo: VTT Technical Research Centre of Finland. Valtion teknillinen tutkimuskeskus. Tiedotteita, No. 605
Karnani, Hari. / Chemical methods for the use of niobium from pressure vessel cladding as a fast neutron dosimeter. Espoo : VTT Technical Research Centre of Finland, 1986. 44 p. (Valtion teknillinen tutkimuskeskus. Tiedotteita; No. 605).
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Karnani, H 1986, Chemical methods for the use of niobium from pressure vessel cladding as a fast neutron dosimeter. Valtion teknillinen tutkimuskeskus. Tiedotteita, no. 605, VTT Technical Research Centre of Finland, Espoo.

Chemical methods for the use of niobium from pressure vessel cladding as a fast neutron dosimeter. / Karnani, Hari.

Espoo : VTT Technical Research Centre of Finland, 1986. 44 p. (Valtion teknillinen tutkimuskeskus. Tiedotteita; No. 605).

Research output: Book/ReportReportProfessional

TY - BOOK

T1 - Chemical methods for the use of niobium from pressure vessel cladding as a fast neutron dosimeter

AU - Karnani, Hari

PY - 1986

Y1 - 1986

N2 - The steel samples from the cladding of a pressure vessel of an operating nuclear power reactor were obtained by scraping. The cladding material of the pressure vessel contained about 0.5 % niobium. It was desired to use the niobium as a dosimeter for estimating fast fluences at the pressure vessel. The weak radiation from the reaction product 93mNb cannot be measured in the presence of other elements and interfering activities. A method was developed to separate niobium from other metals present; the concentration and yield of niobium were determined spectrophotometrically. The irradiated niobium was electrodeposited from aqueous solutions on copper discs. The amount of the deposited niobium was determined by a radiochemical method which makes use of its own radioactivity - measured with a liquid scintillation counter - and the known starting mass of niobium. It was possible to determine the deposited niobium masses (5 to 200 microgram) with a desired degree of accuracy. The absolute emission rate of X-rays could then be measured without any self-absorption or interference from other activities. The mass of niobium on each preparate and its X-ray emission rate, later on, were used as basic experimental data for the estimation of last neutron doses at the pressure vessel.

AB - The steel samples from the cladding of a pressure vessel of an operating nuclear power reactor were obtained by scraping. The cladding material of the pressure vessel contained about 0.5 % niobium. It was desired to use the niobium as a dosimeter for estimating fast fluences at the pressure vessel. The weak radiation from the reaction product 93mNb cannot be measured in the presence of other elements and interfering activities. A method was developed to separate niobium from other metals present; the concentration and yield of niobium were determined spectrophotometrically. The irradiated niobium was electrodeposited from aqueous solutions on copper discs. The amount of the deposited niobium was determined by a radiochemical method which makes use of its own radioactivity - measured with a liquid scintillation counter - and the known starting mass of niobium. It was possible to determine the deposited niobium masses (5 to 200 microgram) with a desired degree of accuracy. The absolute emission rate of X-rays could then be measured without any self-absorption or interference from other activities. The mass of niobium on each preparate and its X-ray emission rate, later on, were used as basic experimental data for the estimation of last neutron doses at the pressure vessel.

KW - nuclear reactors

KW - fast neutrons

KW - fluence

KW - niobium

KW - electrodeposition

KW - pressure vessels

KW - liquid scintilation counting

M3 - Report

SN - 951-38-2600-7

T3 - Tiedotteita / Valtion teknillinen tutkimuskeskus

BT - Chemical methods for the use of niobium from pressure vessel cladding as a fast neutron dosimeter

PB - VTT Technical Research Centre of Finland

CY - Espoo

ER -

Karnani H. Chemical methods for the use of niobium from pressure vessel cladding as a fast neutron dosimeter. Espoo: VTT Technical Research Centre of Finland, 1986. 44 p. (Valtion teknillinen tutkimuskeskus. Tiedotteita; No. 605).