-
2
-
-
0005545602
-
Format and content of report for thermal annealing of reactor pressure vessels
-
U.S. Nuclear Regulatory Commission, Washington, D.C., February
-
"Format and Content of Report for Thermal Annealing of Reactor Pressure Vessels," Regulatory Guide 1.162, U.S. Nuclear Regulatory Commission, Washington, D.C., February 1996.
-
(1996)
Regulatory Guide 1.162
-
-
-
3
-
-
0005552070
-
Radiation embrittlement of reactor vessel materials
-
U.S. Nuclear Regulatory Commission, Washington, D. C., May
-
"Radiation Embrittlement of Reactor Vessel Materials," Regulatory Guide 1.99, Rev. 2, U.S. Nuclear Regulatory Commission, Washington, D. C., May 1988.
-
(1988)
Regulatory Guide 1.99, Rev. 2
-
-
-
4
-
-
0025510514
-
A semiautomated computer-interactive dynamic impact testing system
-
A. A. Braun, N. E. Ashbaugh, and F. M. Smith, Eds., American Society for Testing and Materials, Philadelphia
-
Alexander, D. J., Nanstad, R. K. Corwin, W. R., and Hutton, J. T., "A Semiautomated computer-Interactive Dynamic Impact Testing System," Applications of Automation Technology to Fatigue and Fracture Testing, ASTM STP 1092, A. A. Braun, N. E. Ashbaugh, and F. M. Smith, Eds., American Society for Testing and Materials, Philadelphia, 1990, pp., 83-94.
-
(1990)
Applications of Automation Technology to Fatigue and Fracture Testing, ASTM STP
, vol.1092
, pp. 83-94
-
-
Alexander, D.J.1
Nanstad, R.K.2
Corwin, W.R.3
Hutton, J.T.4
-
5
-
-
0025512124
-
A computer-controlled automated test system for fatigue and fracture testing
-
A. A. Braun, N. E. Ashbaugh, and F. M. Smith, Eds., American Society for Testing and Materials, Philadelphia
-
Nanstad, R. K., Alexander, D. J., Swain, R. L., Hutton, J. T., and Thomas, D. L., "A Computer-Controlled Automated Test System for Fatigue and Fracture Testing," Applications of Automation Technology to Fatigue and Fracture Testing, ASTM STP 1092, A. A. Braun, N. E. Ashbaugh, and F. M. Smith, Eds., American Society for Testing and Materials, Philadelphia, 1990, pp., 7-20.
-
(1990)
Applications of Automation Technology to Fatigue and Fracture Testing, ASTM STP
, vol.1092
, pp. 7-20
-
-
Nanstad, R.K.1
Alexander, D.J.2
Swain, R.L.3
Hutton, J.T.4
Thomas, D.L.5
-
6
-
-
30644477893
-
Pressure vessel annealing for Plant Life Management (PLM); Tensile and hardness properties of irradiated, annealed and re-irradiated low alloy steel
-
Ed. R. Gillot, SMIRT (Stuttgart)
-
th Intl. Conf. on Structural Mechanics in Reactor Technology, Ed. R. Gillot, SMIRT (Stuttgart), 1993, Vol. DG03/3, pp. 409-414.
-
(1993)
th Intl. Conf. on Structural Mechanics in Reactor Technology
, vol.DG03-3
, pp. 409-414
-
-
Tipping, Ph.1
Cripps, R.2
-
7
-
-
30644479649
-
Improved embrittlement correlations for reactor pressure vessel steels
-
November
-
Eason, E. D., Wright, J. E., and Odette, G. R., "Improved Embrittlement Correlations for Reactor Pressure Vessel Steels," NUREG/CR-6551 (MCS 970501), November 1998.
-
(1998)
NUREG/CR-6551 (MCS 970501)
-
-
Eason, E.D.1
Wright, J.E.2
Odette, G.R.3
-
8
-
-
0022231298
-
Relationship between irradiation hardening and embrittlement of pressure vessel steels
-
F. A. Gamer and J. S. Perrin, Eds., American Society for Testing and Materials, Philadelphia
-
Odette, G. R., Lomborzo, P. M., and Wullaert, R. A., "Relationship Between Irradiation Hardening and Embrittlement of Pressure Vessel Steels, " pp. 840-60 in Effects of Radiation on Materials: Twelfth International Symposium, ASTM STP 870, F. A. Gamer and J. S. Perrin, Eds., American Society for Testing and Materials, Philadelphia, 1985.
-
(1985)
Effects of Radiation on Materials: Twelfth International Symposium, ASTM STP
, vol.870
, pp. 840-860
-
-
Odette, G.R.1
Lomborzo, P.M.2
Wullaert, R.A.3
-
9
-
-
0028194479
-
Effects of irradiation temperature on charpy and tensile properties of high-copper, low upper-shelf, submerged-ARC welds
-
A. S. Kumar, D. S. Gelles, R. K. Nanstad, and E. A. Little, Eds., American Society for Testing and Materials, Philadelphia
-
th International Symposium, ASTM STP 1175, A. S. Kumar, D. S. Gelles, R. K. Nanstad, and E. A. Little, Eds., American Society for Testing and Materials, Philadelphia, 1993.
-
(1993)
th International Symposium, ASTM STP
, vol.1175
-
-
Nanstad, R.K.1
Berggren, R.G.2
-
10
-
-
30644456877
-
Status of CRP-4 on MC -brief summary and results
-
17-19 September 2001, TWG-LMNPP-01/3, IAEA, Vienna, Austria
-
Brumovsky, Milan, Wallin, Kim, and Gillemot, Ferenc, "Status of CRP-4 on MC -Brief Summary and Results," Master Curve Testing and Results Application, Proceedings of the IAEA Technical Meeting held in Prague, Czech Republic, 17-19 September 2001, TWG-LMNPP-01/3, IAEA, Vienna, Austria, 2002, pp. 25-40.
-
(2002)
Master Curve Testing and Results Application, Proceedings of the IAEA Technical Meeting Held in Prague, Czech Republic
, pp. 25-40
-
-
Brumovsky, M.1
Wallin, K.2
Gillemot, F.3
-
11
-
-
0348094716
-
Jc and charpy impact toughness for reactor pressure vessel steels
-
November
-
Jc and Charpy Impact Toughness for Reactor Pressure Vessel Steels," NUREG/CR-6609, November 2000.
-
(2000)
NUREG/CR-6609
-
-
Sokolov, M.A.1
Nanstad, R.K.2
-
12
-
-
0033344234
-
Jc and charpy impact toughness for reactor pressure vessel steels
-
R. K. Nanstad, M. L. Hamilton, F. A. Gamer, and A. S. Kumar, Eds., American Society for Testing and Materials, West Conshohocken, PA
-
th International Symposium, ASTM STP 1325, R. K. Nanstad, M. L. Hamilton, F. A. Gamer, and A. S. Kumar, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1999.
-
(1999)
th International Symposium, ASTM STP
, vol.1325
-
-
Sokolov, M.A.1
Nanstad, R.K.2
|