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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
Determination of the Neutron Flux for the Yankee Rowe Experiment in the Ford Nuclear Reactor
By
RJ Cacciapouti
,
RJ Cacciapouti
1
Manager
, Reactor Physics, Yankee Atomic Electric Company
, Bolton, Ma 01581
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L Petrusha
L Petrusha
2
Davis-Besse Resident Engineer
, B&W Nuclear Technologies
, Lynchburg, VA 24502
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Page Count:
10
-
Published:1994
Citation
Cacciapouti, R, & Petrusha, L. "Determination of the Neutron Flux for the Yankee Rowe Experiment in the Ford Nuclear Reactor." 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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Yankee Atomic Electric Company undertook a Test Irradiation Program at the Ford Nuclear Reactor of the University of Michigan. The program was implemented to characterize the irradiation response of representative Yankee Rowe reactor vessel beltline plate materials. The program was also intended to remove uncertainties in the existing reactor vessel fluence and damage predictions on the Yankee Rowe reactor vessel steel. Since this is the first in-core experiment of this type for the Ford Nuclear Reactor, the measurement of the reaction rate and the estimate of the fluence are presented.
References
1.
Biemiller
, Eric B.
, Fyfitch
, Stephen
, Campbell
, Christine A.
, “Preliminary Irradiation Test Results from the Yankee Atomic Electric Company Reactor Vessel Test Program
,” presented at The 1993 ASME Pressure Vessels & Piping Conference, July 25–29, 1993, Denver Colorado
.2.
Biemiller
, Eric B.
, Fyfitch
, Stephen
, Campbell
, Christine A.
, “Preliminary Irradiation Test Results from the Yankee Atomic Electric Company Reactor Vessel Test Program
,” presented at The 12th International Conference on Structural Mechanics in Reactor Technology (SMiRT), August 15–20, 1993, Stuttgart, Germany
.3.
McGarry
, E. D.
, Rogers
, J.
, Prillinger
, G.
, and Hawthorne
, J. R.
, “Consideration of Calculated and Experimental Neutron Dosimetry for Out-of-Core Metallurgy Irradiation Experiments at the Buffalo Reactor
,” Effects of Radiation on Materials: 14th International Symposium (Volume II), ASTM STP 1046.4.
Hawthorne
J. R.
personal communication.
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