DocumentCode
1341678
Title
Neutron Dosimetry and 3-D Neutron Transport Calculations as Toolkit at HFR Petten for Detailed Neutron Monitoring and Damage Analysis
Author
Mutnuru, Ravi Kiran ; Ketema, Dik J. ; Van der Marck, Steven C.
Author_Institution
Nucl. Res. & consultancy Group (NRG), Petten, Netherlands
Volume
57
Issue
6
fYear
2010
Firstpage
3683
Lastpage
3686
Abstract
Dosimetry at the High Flux Reactor in Petten, the Netherlands, serves a variety of purposes ranging from demonstrating compliance with the license for operating the reactor to validating the predictions of displacements per atom (DPA) in material irradiations. It is also used in the validation of the 3-D neutron transport calculations during post-irradiation analysis to normalize the spectrum obtained from these calculations. In this paper, a thorough examination of irradiated steel specimens is carried out using the measurements performed with the neutron activation technique as well as the 3-D neutron transport calculations to check the consistency in the resulting DPA values.
Keywords
dosimetry; fission research reactors; neutrons; 3D neutron transport calculation; HFR Petten; High Flux Reactor; Netherlands; damage analysis; neutron dosimetry; neutron monitoring; Dosimetry; Monitoring; Monte Carlo methods; Neutrons; Radiation effects; Activation foils; Monte Carlo N-Particle Transport Code (MCNP); displacements per atom (DPA); material damage; neutron dosimetry;
fLanguage
English
Journal_Title
Nuclear Science, IEEE Transactions on
Publisher
ieee
ISSN
0018-9499
Type
jour
DOI
10.1109/TNS.2010.2075940
Filename
5593908
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