Issue |
EPJ Web of Conferences
Volume 106, 2016
ISRD 15 – International Symposium on Reactor Dosimetry
|
|
---|---|---|
Article Number | 02003 | |
Number of page(s) | 8 | |
Section | Reactor Surveillance and Plant Life | |
DOI | https://doi.org/10.1051/epjconf/201610602003 | |
Published online | 03 February 2016 |
https://doi.org/10.1051/epjconf/201610602003
Lifetime Neutron Fluence Analysis of the Ringhals Unit 1 Boiling Water Reactor
1 Westinghouse Electric Company LLC 1000 Westinghouse Drive, Cranberry Township, PA 16066, USA
2 Vattenfall/Ringhals AB, 432 85 Väröbacka, Sweden
a Corresponding author: jkulesza@umich.edu
Published online: 3 February 2016
This paper describes a neutron fluence assessment considering the entire commercial operating history (35 cycles or ∼ 25 effective full power years) of the Ringhals Unit 1 reactor pressure vessel beltline region. In this assessment, neutron (E >1.0 MeV) fluence and iron atom displacement distributions were calculated on the moderator tank and reactor pressure vessel structures. To validate those calculations, five in-vessel surveillance chain dosimetry sets were evaluated as well as material samples taken from the upper core grid and wide range neutron monitor tubes to act as a form of retrospective dosimetry. During the analysis, it was recognized that delays in characterizing the retrospective dosimetry samples reduced the amount of reactions available to be counted and complicated the material composition determination. However, the comparisons between the surveillance chain dosimetry measurements (M) and calculated (C) results show similar and consistent results with the linear average M/C ratio of 1.13 which is in good agreement with the resultant least squares best estimate (BE)/C ratios of 1.10 for both neutron (E >1.0 MeV) flux and iron atom displacement rate.
© 2014 Westinghouse Electric Company LLC. All Rights Reserved
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