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ASTM Selected Technical Papers
Reactor Dosimetry: 14th International Symposium
By
David W. Vehar
David W. Vehar
JAI Guest Editor
1
Sandia National Laboratories
,
Albuquerque, New Mexico,
US
Search for other works by this author on:
Douglas L. Selby
Douglas L. Selby
JAI Guest Editor
2
Oak Ridge National Laboratory
,
Oak Ridge, TN,
US
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Mary Helen Sparks
Mary Helen Sparks
JAI Guest Editor
3
White Sands Missile Range
,
White Sands, NM,
US
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ISBN:
978-0-8031-7536-5
No. of Pages:
794
Publisher:
ASTM International
Publication date:
2012

Interpretation of reactor dosimetry experiments with C/E comparison requires precise knowledge of parameters involved in modeling. Some parameters have more weight than others on the calculated values. So, sensitivity studies should be conducted to verify the importance of these parameters. The conclusions of these studies are used to refine the experiment modeling, or to correct uncertainty calculations. The results of these sensitivity studies allow a post-irradiation analysis, which can justify the discarding of some atypical C/M values. Derived uncertainties may be improved by the sensitivity analyses. Beyond classical parameters as geometry or composition, this paper describes some specific sensitivity studies conducted for dosimetry irradiation in reactor, and presents conclusions. These studies are based on dosimeters irradiated in the EOLE reactor facility at Cadarache CEA center. Conclusions drawn from these studies are generic and can be applied to any dosimetry study. Calculations performed for these studies were realized using TRIPOLI-4 Monte Carlo code.

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