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ASTM Selected Technical Papers
Reactor Dosimetry
By
H Farrar, IV IV,
H Farrar, IV IV
1
Symposium General Chairman Consultant Bell Canyon, California
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EP Lippincott,
EP Lippincott
2
Program Committee Chairman
?Westinghouse
?Pittsburgh, Pennsylvania
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JG Williams,
JG Williams
3
Program Committee Vice Chairman
?University of Arizona
?Tucson, Arizona
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DW Vehar
DW Vehar
4
Scientific Secretary
?Sandia National Laboratories
?Albuquerque, New Mexico
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ISBN-10:
0-8031-1899-6
ISBN:
978-0-8031-1899-7
No. of Pages:
131
Publisher:
ASTM International
Publication date:
1994
eBook Chapter
Assessment of Uncertainty in Reactor Vessel Fluence Determination
By
EP Lippincott
EP Lippincott
1
Senior Engineer
, Westinghouse Electric Corporation
, PO Box 355, Pittsburgh, PA 15230
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Page Count:
9
-
Published:1994
Citation
Lippincott, E. "Assessment of Uncertainty in Reactor Vessel Fluence Determination." Reactor Dosimetry. Ed. Farrar, H, IV, Lippincott, E, Williams, J, & Vehar, D. 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959 : ASTM International, 1994.
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Evaluation of neutron fluence for reactor vessels is important for evaluation of irradiation damage that may limit vessel life. The uncertainty in calculated fluence is considered to be typically about 20%. Benchmark measurements have improved confidence in the uncertainty assessments and enable testing of improved cross section data and calculational procedures. Use of appropriate plant-specific measurements can lower uncertainty substantially below 20% for some cases and also can limit the effects of unknown errors that may cause larger deviations.
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, Eds., American Society for Testing and Materials
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.
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