A new approach that utilizes the information fusion technique was developed to predict the radiation embrittlement of reactor pressure vessel (RPV) steels. The Charpy transition temperature-shift data is used as the primary index of the RPV radiation embrittlement in this study. Six parameters, Cu, Ni, P, neutron fluence, irradiation time, and irradiation temperature are used in the embrittlement prediction models. The results indicate that this new embrittlement predictor achieved about 66% and 53% reductions, respectively, in the uncertainties for the update General Electric (GE) Boiling Water Reactor (BWR) plate and weld data compared to the Nuclear Regulatory Commission (NRC) Regulatory Guide 1.99, Rev. 2 (RG1.99/R2). The implications of irradiation temperature effects for the development of radiation embrittlement models are also discussed.
1.
Wang, J. A., August 1997, Embrittlement Data Base, Version 1, NUREG/CR-6506 (ORNL/TM-13327), U.S. Nuclear Regulatory Commission.
2.
Stallmann, F. W., Wang, J. A., Kam, F. B. K., and Taylor, B. J., 1994, “PR-EDB: Power Reactor Embrittlement Data Base, Version 2,” NUREG/CR-4816, ORNL/TM-10328/R2.
3.
Rao
, N. S. V.
, 1999
, “Multiple Sensor Fusion Under Unknown Distributions
,” J. Franklin Institute
, 336
, no. 2
, pp. 285
–299
.4.
Rao, N. S. V., 2002, “Multisensor Fusion Under Unknown Distributions: Finite Sample Performance Guarantees,” in Multisensor Fusion, Proc. NATO Adv. Study Institute on Multisensor Data Fusion, Perthshire, Scotland, June 25–July 7, Springer, Berlin, Germany.
5.
Rao
, N. S. V.
, 2001
, “On Fusers That Perform Better Than Best Sensor
,” IEEE Trans. Pattern Anal. Mach. Intell.
, 23
, no. 8
, pp. 904
–909
.6.
Duda, R. O., Hart, P. E., and Stork, D. G., 2001, Pattern Classification, 2nd ed. (Wiley, New York).
7.
Rao
, N. S. V.
, and Protopopescu
, V.
, 1996
, “On PAC Learning of Functions With Smoothness Properties Using Feedforward Sigmoidal Networks
,” Proc. IEEE
, 84
, no. 10
, pp. 1562
–1569
.8.
Wang, J. A., March 1999, “Development of Embrittlement Prediction Models for U.S. Power Reactors,” pp. 525–540 in Effect of Radiation on Materials: 18th International Symposium, ASTM STP 1325.
9.
Rao, N. S., 2002, “Nearest Neighbor Projective Fuser for Function Estimation,” Proc. Conf. On Information Fusion.
10.
Mansur, L. K., 1987, “Mechanisms and Kinetics of Radiation Effects in Metals and Alloys,” Kinetics of Nohomogeneous Processes, ed. by Gorden R. Freeman.
11.
Wang, J. A., March 2000, “Analysis of the Irradiated Data for A302B and A533B Correlation Monitor Materials,” pp. 59–80 in Effect of Radiation on Materials: 19th International Symposium ASTM STP 1366, ASTM, Philadelphia.
12.
Wang, J. A., Kam, F. B. K., and Stallmann, F. W., August, 1996, “Embrittlement Data Base (EDB) and Its Applications,” Effects of Radiation on Materials: Vol. 17, ASTM STP 1270, pp. 500–521.
13.
Guthrie, G. L., 1983, Charpy Trend Curves Based on 177 PWR Data Points, NUREG/CR-3391, U.S. Nuclear Regulatory Commission.
14.
Odette, G. R., Lombrozo, P. M., Perrin, J. F., and Wullaert, R. A., 1984, Physically Based Regression Correlations of Embrittlement Data From Reactor Pressure Vessel Surveillance Programs, EPRI NP-3319, Electric Power Research Institute.
15.
Fisher, S. B., and Buswell, J. T., 1986, A Model for PWR Pressure Vessel Embrittlement, Berkeley Nuclear Laboratories, Central Electric Generating Board, GL139PB.
16.
Lowe, A. L., Jr., and Pegram, J. W., May 1991, Correlations for Predicting the Effects of Neutron Radiation on Linde 80 Submerged-Arc Welds, BAW-1803, Rev. 1.
17.
Brillaud, C., Hedin, F., and Houssin, B., 1987, “A Comparison Between French Surveillance Program Results and Predictions of Irradiation Embrittlement,” Influence of Radiation on Material Properties, ASTM STP 956, pp. 420–447.
18.
Randall, P. N., 1986, “Basis for Revision 2 of the U.S. Nuclear Regulatory Commission’s Regulatory Guide 199,” Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Second Volume), ASTM STP 909, pp. 149–162.
19.
Eason, E. D., Wright, J. E., and Odette, G. R., 2000, Improved Embrittlement Correlations for Reactor Pressure Vessel Steels, NUREG/CR-6551, U.S. Nuclear Regulatory Commission.
20.
Hassoun, M. H., 1995, Fundamentals of Artificial Neural Networks (MIT Press,
21.
Rao
, N. S. V.
, 2000
, “Finite Sample Performance Guarantees of Fusers for Function Estimators
,” Information Fusion
, 1
, no. 1
, pp. 35
–44
.Copyright © 2005
by ASME
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