Retrospective Dosimetry of Fast Neutrons Focused on the Reactions 93Nb(n,n´)93Nbm and 54Fe(n,p)54Mn

W. P. Voorbraak, Tommi Kekki, Tom Seré n, M. Van Bockxstaele, J. Wagemans, J. R. W. Woittiez

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsProfessional

Abstract

An overview is given of practices for retrospective dosimetry based on extraction and counting of niobium and manganese present in typical pressure vessel materials. The main problem of counting structural materials is the overwhelming presence of the nuclide 60Co in the gamma-ray spectra of irradiated materials. Chemical separation of niobium and manganese is needed to determine the induced 93Nbm and 54Mn activities. Procedures have been developed for retrospective dosimetry applicable at normally equipped radiochemical laboratories. Chemical separation procedures have been applied followed by determination of the amount of niobium in dissolution after separation. Special attention has been given to the accurate counting of the very weak X rays of 93Nbm. Different techniques have been applied. Advantages, disadvantages, and the accuracy that can be achieved are discussed. Special attention has been given to the maximum accuracy that can be reached and the minimum amount of niobium that has to be collected to reach this accuracy.
Original languageEnglish
Title of host publicationProceedings of the 12th International Symposium on Reactor Dosimetry
PublisherAmerican Society for Testing and Materials ASTM
Pages416-423
ISBN (Print)9780803134126
Publication statusPublished - 2008
MoE publication typeD3 Professional conference proceedings
Event12th International Symposium on Reactor Dosimetry - Gatlinburg, TN, United States
Duration: 8 May 200513 May 2005

Publication series

SeriesASTM Special Technical Publication
ISSN0066-0558

Conference

Conference12th International Symposium on Reactor Dosimetry
CountryUnited States
CityGatlinburg, TN
Period8/05/0513/05/05

Fingerprint

Niobium
Dosimetry
Neutrons
Manganese
Pressure vessels
Gamma rays
Isotopes
Dissolution
X rays

Keywords

  • retrospective dosimetry
  • neutron fluence
  • neutron damage
  • niobium
  • manganese
  • column anion exchange
  • liquid scintillation counting
  • neutron activation analysis

Cite this

Voorbraak, W. P., Kekki, T., Seré n, T., Van Bockxstaele, M., Wagemans, J., & Woittiez, J. R. W. (2008). Retrospective Dosimetry of Fast Neutrons Focused on the Reactions 93Nb(n,n´)93Nbm and 54Fe(n,p)54Mn. In Proceedings of the 12th International Symposium on Reactor Dosimetry (pp. 416-423). American Society for Testing and Materials ASTM. ASTM Special Technical Publication
Voorbraak, W. P. ; Kekki, Tommi ; Seré n, Tom ; Van Bockxstaele, M. ; Wagemans, J. ; Woittiez, J. R. W. / Retrospective Dosimetry of Fast Neutrons Focused on the Reactions 93Nb(n,n´)93Nbm and 54Fe(n,p)54Mn. Proceedings of the 12th International Symposium on Reactor Dosimetry. American Society for Testing and Materials ASTM, 2008. pp. 416-423 (ASTM Special Technical Publication).
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abstract = "An overview is given of practices for retrospective dosimetry based on extraction and counting of niobium and manganese present in typical pressure vessel materials. The main problem of counting structural materials is the overwhelming presence of the nuclide 60Co in the gamma-ray spectra of irradiated materials. Chemical separation of niobium and manganese is needed to determine the induced 93Nbm and 54Mn activities. Procedures have been developed for retrospective dosimetry applicable at normally equipped radiochemical laboratories. Chemical separation procedures have been applied followed by determination of the amount of niobium in dissolution after separation. Special attention has been given to the accurate counting of the very weak X rays of 93Nbm. Different techniques have been applied. Advantages, disadvantages, and the accuracy that can be achieved are discussed. Special attention has been given to the maximum accuracy that can be reached and the minimum amount of niobium that has to be collected to reach this accuracy.",
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Voorbraak, WP, Kekki, T, Seré n, T, Van Bockxstaele, M, Wagemans, J & Woittiez, JRW 2008, Retrospective Dosimetry of Fast Neutrons Focused on the Reactions 93Nb(n,n´)93Nbm and 54Fe(n,p)54Mn. in Proceedings of the 12th International Symposium on Reactor Dosimetry. American Society for Testing and Materials ASTM, ASTM Special Technical Publication, pp. 416-423, 12th International Symposium on Reactor Dosimetry, Gatlinburg, TN, United States, 8/05/05.

Retrospective Dosimetry of Fast Neutrons Focused on the Reactions 93Nb(n,n´)93Nbm and 54Fe(n,p)54Mn. / Voorbraak, W. P.; Kekki, Tommi; Seré n, Tom; Van Bockxstaele, M.; Wagemans, J.; Woittiez, J. R. W.

Proceedings of the 12th International Symposium on Reactor Dosimetry. American Society for Testing and Materials ASTM, 2008. p. 416-423 (ASTM Special Technical Publication).

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsProfessional

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AU - Voorbraak, W. P.

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AU - Seré n, Tom

AU - Van Bockxstaele, M.

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N2 - An overview is given of practices for retrospective dosimetry based on extraction and counting of niobium and manganese present in typical pressure vessel materials. The main problem of counting structural materials is the overwhelming presence of the nuclide 60Co in the gamma-ray spectra of irradiated materials. Chemical separation of niobium and manganese is needed to determine the induced 93Nbm and 54Mn activities. Procedures have been developed for retrospective dosimetry applicable at normally equipped radiochemical laboratories. Chemical separation procedures have been applied followed by determination of the amount of niobium in dissolution after separation. Special attention has been given to the accurate counting of the very weak X rays of 93Nbm. Different techniques have been applied. Advantages, disadvantages, and the accuracy that can be achieved are discussed. Special attention has been given to the maximum accuracy that can be reached and the minimum amount of niobium that has to be collected to reach this accuracy.

AB - An overview is given of practices for retrospective dosimetry based on extraction and counting of niobium and manganese present in typical pressure vessel materials. The main problem of counting structural materials is the overwhelming presence of the nuclide 60Co in the gamma-ray spectra of irradiated materials. Chemical separation of niobium and manganese is needed to determine the induced 93Nbm and 54Mn activities. Procedures have been developed for retrospective dosimetry applicable at normally equipped radiochemical laboratories. Chemical separation procedures have been applied followed by determination of the amount of niobium in dissolution after separation. Special attention has been given to the accurate counting of the very weak X rays of 93Nbm. Different techniques have been applied. Advantages, disadvantages, and the accuracy that can be achieved are discussed. Special attention has been given to the maximum accuracy that can be reached and the minimum amount of niobium that has to be collected to reach this accuracy.

KW - retrospective dosimetry

KW - neutron fluence

KW - neutron damage

KW - niobium

KW - manganese

KW - column anion exchange

KW - liquid scintillation counting

KW - neutron activation analysis

M3 - Conference article in proceedings

SN - 9780803134126

T3 - ASTM Special Technical Publication

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BT - Proceedings of the 12th International Symposium on Reactor Dosimetry

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Voorbraak WP, Kekki T, Seré n T, Van Bockxstaele M, Wagemans J, Woittiez JRW. Retrospective Dosimetry of Fast Neutrons Focused on the Reactions 93Nb(n,n´)93Nbm and 54Fe(n,p)54Mn. In Proceedings of the 12th International Symposium on Reactor Dosimetry. American Society for Testing and Materials ASTM. 2008. p. 416-423. (ASTM Special Technical Publication).