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ASTM Selected Technical Papers
Effects of Radiation on Materials: 19th International Symposium
By
ML Hamilton
ML Hamilton
editor
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AS Kumar
AS Kumar
editor
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ST Rosinski
ST Rosinski
editor
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ML Grossbeck
ML Grossbeck
editor
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ISBN-10:
0-8031-2852-5
ISBN:
978-0-8031-2852-1
No. of Pages:
1286
Publisher:
ASTM International
Publication date:
2000

Recently, a new predictive model has been developed by the NRC and is being implemented in ASTM Standard E 900, that addresses radiation-induced embrittlement of ferritic steels. The model is based on extensive Charpy impact energy data of irradiated reactor vessel steels obtained from surveillance programs. The final application of this new method is to predict fracture toughness of irradiated materials to determine pressure-temperature curves for nuclear power plant operation and RTPTS values in compliance with the current regulatory rules for the nuclear-utility industry.

In this paper, the predicted fracture toughness of irradiated reactor vessel welds is compared with that of irradiated material. The degree of conservatism in the Charpy impact energy based predictive model is assessed by comparison with the actual fracture toughness of irradiated materials.

1.
1998 ASME Boiler and Pressure Vessel Code, Section XI,
Rules for Inservice Inspection of Nuclear Power Plant Components
,
the American Society of Mechanical Engineers
,
New York, New York
,
01
07
1998
.
2.
Draft Revision of ASTM Standard E 900, “
Standard Guide for Predicting Neutron Radiation Damage to Reactor Vessel Materials
,” ASTM Ballot,
28
04
1998
.
3.
U. S. Regulatory Commission
, “
Radiation Embrittlement Damage to Reactor Vessel Materials
,”
Regulatory Guide
1.99
, Rev. 2,
05
1988
.
4.
Nanstad
,
R. K.
,
Haggag
,
F. M.
,
McCabe
,
D. E.
,
Iskander
,
S. K.
,
Bowman
,
K. O.
, and
Menke
,
B. H.
,
1992
, “
Irradiation Effects on Fracture Toughness of Two High Copper Submerged-Arc Welds, HSSI Series 5
,” NUREG/CR-5913,
Oak Ridge National Laboratory
.
5.
McCabe
,
D. E.
,
Sokolov
,
M. A.
,
Nanstad
,
R. K.
, and
Swain
R.L.
, “
Effects of Irradiation to 0.5 and 1.0e19 neutrons/cm**2 (>1MeV) on the Midland Reactor Low Upper-shelf Weld: Capsules 10.01, 10.02, and 10.05 in the Heavy-Section Steel Irradiation Program 10th Irradiation Series
,”
08
1995
, ORNL/NRC/LTR-95/18.
6.
BAW-2254P, “
Test Results of Capsule CR3-LG2 B&W Owners Group
,”
Framatome Technologies, Inc.
,
10
1995
.
7.
Code Case N-629, Boiler and Pressure Vessel Code,
American Society of Mechanical Engineer
,
1999
.
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