Small punch tests on steels for steam power plant(I)

Baik J. M., Kameda J., and Buck O., 1986, “Development of Small Punch Tests for Ductile-brittle Transition Temperature Measurement of Temper Embrittlement Ni−Cr Steels,”The Use of Small scale Specimens for Testing Irradiated Material, ASTM STP 888, W. R. Corwin and G. E. Lucas, Eds. American Society for Testing and Materials, Philadelphia, U. S. A., pp. 92–111.

Choi H. C., Chung Y. K, Kim H. K, and Park J. J., 1996, “Material Property Studies of a Retired Superheater Header for Remaining Life Assessment,”in Risk, Economy and Safety, Failure Minimisation and Analysis, Fenny Eds., Rotterdam, pp. 337–348.

Eto M., Takahashi H., Misawa T., Suzuki M., Nishiyama Y., Fukaya Y., and Jitsukawa S., 1993, “Development of a Miniaturized Bulge Test for Post-Irradiation Mechanical Property Evaluation,”Small Specimen Tests Techniques Applied to Nuclear Reactor Vessel Thermal Annealing and Plant Life Extension, ASTM STP 1204, W. R. Corwin and F. M. Haggar, Eds. American Society for Testing and Materials, Philadelphia, U. S. A., pp. 241–255.

Fleury E. and Ha J. S., 1998, “Small Punch Test on Steels for Steam Power Plant: Part II: Modeling,”KSME International Journal.

Foulds J. and Viswanathan R., 1994, “Small Punch Testing for Determining the Material Toughness of Low Alloy Steel Components in Service,”Journal of Engineering Materials and Technology, Oct. 1994, Vol. 116, pp. 457–464.

Ha J. S., Fleury E., Hyun J. S., Kim K. Y. and Baek S. G., 1997, “High Temperature Small Punch Behaviors of 12Cr Steel for Supercritical Power Plant,” in the proceedings of the Conference organized by KSME, held in Kwangju. Korea, April 25–26, pp. 259–264, (in Korean).

Ha J. S., Kim K. Y., Baek S. G., Kang M. S. and Song G. W., 1996, “The Behaviors of 2Cr-1Mo Steel at High Temperature by Small Punch Test,” in proceedings of the Conference organized by KSME, held in Inchon, pp. 184–188.

Iwadate T., Tanaka Y. and Takemata H., 1994, “Prediction of Fracture Toughness KIC Transition Curves of Pressure Vessel Steels From Charpy V-notch Impact Test Results,”Journal of Pressure Vessel Technology, Nov. 1994, Vol. 116, pp. 353–358.

Lucas G. E., Okada A. and Kiritani M., 1986, “Parametric Analysis of the Disc Bend Test,”Journal of Nuclear Materials, Vol. 141–143, pp. 532–535.

Lucas G. E., 1990, “Review of Small Specimen Test Techniques for Irradiation Testing,”Metallurgical Transactions A, Vol. 21-A, pp. 1105–1119.

Mao X., Saito M. and Takahashi H., 1987, “Characterization of Fracture Behavior in Small Punch test by Combined Recrystallization-Etch method and Rigid Plastic Analysis,”Journal of Testing and Evaluation, Vol. 15, No. 1, pp. 30–37.

Masushita T., Saucedo, M. L., Joo Y. H. and Shoji T., 1991, “DBTT Estimation of Ferritic Low Alloy Steels in Service Plant by Means of Small Punch Test,”Fracture and Strength 1990 Key Engineering Materials, Vol. 51–52, Trans. Tech. Publ., Zurich, Switzerland, p. 259.

Suzuki M., Eto M., Nishiyama Y., Fukaya K., and Isozaki T., 1993, “Estimation of Toughness Degradation by Microhardness and Small Punch Tests,”Small Specimen Test Techniques Applied to Nuclear Reactor Vessel Thermal Annealing and Plant Life Estimation, ASTM STP 1204, W. R. Corwin, F. M. Haggag, and W. L. Server, Eds., American Society for Testing and Materials, Philadelphia, U. S. A., 1993 pp. 217–227.

Viswanathan R. and Wells C. H., 1993, “Life Prediction of Turbine Generator Rotors, Technology for the ’90s,”The ASME Pressure Vessels and Piping Division, M. K. Au-Yang, Ed., pp. 140–177.

Yoo Jin, 1996, “Creep Experiments on High Chromium Steel for Fossil Power Plant,” Final Report, KRC-93G-J02, KAIST Taejon, December 1996, (in Korean).

Yoon Gyung-seok, 1985, “A Study on the Conservation Method of Thermal Power Plant During Idle Period,” Final Report, KRC-84G-J03, KEPRI Taejon, August 1985, (in Korean).