Dosimetry Evaluation of In-Core and Above-Core Zirconium Alloy Samples in a PWR
A description of the neutron fluence analysis of activated zirconium alloys samples at a Westinghouse 3-loop reactor is presented. These samples were irradiated in the core and in the fuel plenum region, where dosimetry measurements are relatively rare compared with regions radially outward of the c...
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2016-01-01
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Series: | EPJ Web of Conferences |
Online Access: | http://dx.doi.org/10.1051/epjconf/201610602005 |
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doaj-59bcc50b665341b8a1cbbf4c7661e2002021-08-02T10:20:27ZengEDP SciencesEPJ Web of Conferences2100-014X2016-01-011060200510.1051/epjconf/201610602005epjconf-ISRD2015_02005Dosimetry Evaluation of In-Core and Above-Core Zirconium Alloy Samples in a PWRAmiri Benjamin W.0Foster John P.1Greenwood Larry R.2Westinghouse Electric Company LLC, Radiation Engineering & AnalysisWestinghouse Electric Company LLCBattelle Pacific Northwest National LaboratoryA description of the neutron fluence analysis of activated zirconium alloys samples at a Westinghouse 3-loop reactor is presented. These samples were irradiated in the core and in the fuel plenum region, where dosimetry measurements are relatively rare compared with regions radially outward of the core. Dosimetry measurements performed by Batelle/PNNL are compared to the calculational models. Good agreement is shown with the in-core measurements when using analysis conditions expected to best represent this region, such as an assembly-specific axial power distribution. However, the use of these conditions to evaluate dosimetry in the fuel plenum region can lead to significant underestimation of the fluence. The use of a flat axial power distribution, however, does not underestimate the fluence in the fuel plenum region.http://dx.doi.org/10.1051/epjconf/201610602005 |
collection |
DOAJ |
language |
English |
format |
Article |
sources |
DOAJ |
author |
Amiri Benjamin W. Foster John P. Greenwood Larry R. |
spellingShingle |
Amiri Benjamin W. Foster John P. Greenwood Larry R. Dosimetry Evaluation of In-Core and Above-Core Zirconium Alloy Samples in a PWR EPJ Web of Conferences |
author_facet |
Amiri Benjamin W. Foster John P. Greenwood Larry R. |
author_sort |
Amiri Benjamin W. |
title |
Dosimetry Evaluation of In-Core and Above-Core Zirconium Alloy Samples in a PWR |
title_short |
Dosimetry Evaluation of In-Core and Above-Core Zirconium Alloy Samples in a PWR |
title_full |
Dosimetry Evaluation of In-Core and Above-Core Zirconium Alloy Samples in a PWR |
title_fullStr |
Dosimetry Evaluation of In-Core and Above-Core Zirconium Alloy Samples in a PWR |
title_full_unstemmed |
Dosimetry Evaluation of In-Core and Above-Core Zirconium Alloy Samples in a PWR |
title_sort |
dosimetry evaluation of in-core and above-core zirconium alloy samples in a pwr |
publisher |
EDP Sciences |
series |
EPJ Web of Conferences |
issn |
2100-014X |
publishDate |
2016-01-01 |
description |
A description of the neutron fluence analysis of activated zirconium alloys samples at a Westinghouse 3-loop reactor is presented. These samples were irradiated in the core and in the fuel plenum region, where dosimetry measurements are relatively rare compared with regions radially outward of the core. Dosimetry measurements performed by Batelle/PNNL are compared to the calculational models. Good agreement is shown with the in-core measurements when using analysis conditions expected to best represent this region, such as an assembly-specific axial power distribution. However, the use of these conditions to evaluate dosimetry in the fuel plenum region can lead to significant underestimation of the fluence. The use of a flat axial power distribution, however, does not underestimate the fluence in the fuel plenum region. |
url |
http://dx.doi.org/10.1051/epjconf/201610602005 |
work_keys_str_mv |
AT amiribenjaminw dosimetryevaluationofincoreandabovecorezirconiumalloysamplesinapwr AT fosterjohnp dosimetryevaluationofincoreandabovecorezirconiumalloysamplesinapwr AT greenwoodlarryr dosimetryevaluationofincoreandabovecorezirconiumalloysamplesinapwr |
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1721233996362285056 |