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ASTM Selected Technical Papers
Reactor Dosimetry: Radiation Metrology and Assessment
By
JG Williams
JG Williams
1
ASTM Program Chair
?
University of Arizona
?
Tucson, AZ
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DW Vehar
DW Vehar
2
Symposium Vice-Chair and Secretary
?
Sandia National Laboratories
?
Albuquerque, NM
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FH Ruddy
FH Ruddy
3
Symposium Chair
?
Westinghouse Science & Technology Ctr.
?
Pittsburgh, PA
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DM Gilliam
DM Gilliam
4
ASTM Program Vice-Chair
?
National Institute of Standards & Technology
?
Gaithersburg, MD
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ISBN-10:
0-8031-2884-3
ISBN:
978-0-8031-2884-2
No. of Pages:
897
Publisher:
ASTM International
Publication date:
2001

Integrity assessment was performed for the reactor vessel of Mihama-1, which started operation early among Japan's PWRs, in view of neutron irradiation Bembrittlement to be undergone after 60 years of operation. Reference temperature RTNDT and upper shelf energy after 60 years of operation was estimated based on the results of surveillance tests. It was confirmed that the fracture toughness evaluation based on the surveillance tests and speculated reference temperature exceeded the stress intensity factor K1 which occurred in the event of pressurized thermal shock, and the decreased upper shelf energy evaluated in accordance with the elasto-plastic fracture mechanics would not lead to the growth of an assumed crack followed by fracture after 60 years of operation. The results of evaluations have demonstrated that the integrity of the Mihama unit No. 1 reactor vessel could be maintained after 60 years of operation.

1.
U.S.Nuclear Regulatory Commission Regulatory Guide 1.161,
1995
. pp.3–8
2.
The Japan Electric Association
, JEAC 4201-1991,
Method of Surveillance Tests for Structural Material of Nuclear Reactors
,
1991
, pp.2,12–14.
3.
The Japan Electric Association
, JEAC 4206-1991,
Method of Verification Tests of the Fracture Toughness for Nuclear Power Plant Components
,
1991
, pp.5,31–39.
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