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Digital Library / STP / STP1175-EB
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Effects of Radiation on Materials: 16th International Symposium
Kumar AE
Pages: 7
Published: 1994
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Table of Contents
Meeting Future Power Needs in Licensing Space
Rossin AD
Usnrc Research on Reactor Pressure Vessel Steel Embrittlement
Taboada A, Mayfield M
Irradiation Creep due to SIPA Under Cascade Damage Conditions
Woo CH, Garner FA, Holt RA
A Model for Interstitial Loop Formation in Concentrated Alloys During Irradiation
Hashimoto T, Shigenaka N
Predictions of Interfacial Phosphorus Segregation in Irradiated Ferritic Steels
Faulkner RG, Little EA
Segregation Effects in Ferritic Fe-Cr Alloys
Gelles DS
Neutron Irradiation Damage and Hardness Anisotropy in Molybdenum Single Crystals
Abe K, Kanzaki M, Satou M, Arai K
Strengthening of Chromium Films by 75 Mev Ni Ion Irradiation
Jain A, Loganathan S, Jaipal , Kanjilal D, Mehta GK
Radiation Damage Rate Measurements in Nickel
Schüle W
Effects of Fission and Fusion Neutron Irradiations on Mechanical Properties and Defect Recovery Behavior in -Iron
Aono Y, Kuramoto E, Yoshida N, Kurishita H, Kayano H
Subsize Specimen Testing of a Nuclear Reactor Pressure Vessel Material
Kumar AS, Rosinski ST, Cannon NS, Hamilton ML
The Effect of Loading Rate Upon Irradiation Embrittlement Measured by Fracture Mechanical Properties
Wallin K, Valo M, Rintamaa R, Ahlstrand R
Effects Of Irradiation Temperature on Embrittlement of Nuclear Pressure Vessel Steels
Haggag FM
Study on the Irradiation Embrittlement of a Microalloyed Ferritic Steel
Ganguly C, Viswanathan UK, Balakrishnan KS
Comparison of Drop-Weight and Instrumented Charpy Impact Test Results for Irradiated RPV Steels
Pachur D
Fracture Toughness and Impact Tests on Neutron Irradiated Ferritic Steels : Results and Correlations
Chatterjee S, Sriharsha HK, Viswanathan UK
Development and Application of an LWR Reactor Pressure Vessel-Specific Flaw Distribution
Rosinski ST, Kennedy EL, Foulds JR
Effects of Irradiation Temperature on Charpy and Tensile Properties of High-Copper, Low Upper-Shelf, Submerged-Arc Welds
Nanstad RK, Berggren RG
Evaluation of Thermal-Aged Plates, Forgings, and Submerged-Arc Weld Metals
DeVan MJ, Lowe AL, Wade CS
Effect of Specimen Size on the Impact Properties of a Pressure Vessel Weld Material
Kumar AS, Cannon NS, Hamilton ML
Further Microstructural Characterization of Submerged-Arc Weld Metals - II
Lawless KR, Lowe AL
Exploratory Studies of the Effects of Irradiation Temperature on Mechanical Properties of Structural Steels amd Welds
Hawthorne JR
The Radiation Hardening and Embrittlement of a Mild Steel Submerged-Arc Weld
Buswell JT, Bolton CJ, Wootton MR, Bischler PJE, Jones RB, Jones LT, Phythian WJ, Sinclair RR
Annealing Experiments on Irradiated NiCrMo Weld Metal
Leitz C, Klausnitzer EN, Hofmann G
Degradation of Mechanical Properties of Stainless Steel Cladding Due to Neutron Irradiation and Thermal Aging
Haggag FM
The Effect of Flux on the Irradiation Hardening of Pressure Vessel Steels
Odette GR, Mader EV, Lucas GE, Phythian WJ, English CA
Modeling the Influence of Irradiation Temperature and Displacement Rate on Hardening Due to Point Defect Clusters in Ferritic Steels
Stoller RE
The Modelling of Radiation Hardening and Embrittlement in Magnox Mild Steel Submerged-Arc Welds
Buswell JT, Jones RB
Irradiation Induced Precipitation in Model Alloys with Systematic Variation of Cu, Ni and P Content: A Small Angle Neutron Scattering Study
Solt G, Frisius F, Waeber WB, Tipping P
Characterisation of Model Fe-Cu-Mn-Ti-N Alloys by Electron Microscopy and Positron Annihilation
Phythian WJ, de Diego N, Mace J, McElroy RJ
An APFIM Survey of Grain Boundary Segregation and Precipitation in Irradiated Pressure Vessel Steels
Miller MK, Burke MG
Investigation of Neutron Irradiated Soviet-type Reactor Pressure Vessel Steels by Small Angle Neutron Scattering
Brauer G, Eichhorn F, Frisius F, Kampmann R
Influence of Some Alloying Elements on the Formation of Vacancy Defects in Ferritic Steels During Irradiation at 288°C
Akamatsu M, Dai G, Li X, Moser P, Van Duysen JC, Zacharie G
Metallurgical Considerations in the Application of DPA to Reactor Vessel Analysis
Harbison LS, Lowe AL
Postirradiation Deformation Behavior in Ferritic Fe-Cr Alloys
Hamilton ML, Gelles DS, Gardner PL
Tensile and Fracture Mechanics Properties of Neutron Irradiated Manet I (Martensitic 11Cr Steel Type DIN 1.4914)
de Vries MI
Influence of Cold Work, Heat Treatment, and Chromium Content on the Fracture Properties of Irradiated Martensitic Steels
Huang FH
Charpy Impact Toughness of Martensitic Steels Irradiated in FFTF: Effect of Heat Treatment
Klueh RL, Alexander DJ
Microstructural Studies in Fast Reactor Irradiated FV448 Ferritic-Martensitic Alloy Plate and Weldment
Morgan TS, Little EA, Faulkner RG
Effects of Neutron Irradiation on the Notch Ductility of 15MnTi Steel
Aixin YJ, Han RP
The Influence of Specimen Size on Measurement of Thermal or Irradiation Creep in Pressurized Tubes
Garner FA, Hamilton ML, Puigh RJ, Eiholzer CR, Duncan DR, Toloczko MB, Kumar AS
Tensile Properties of Neutron Irradiated 316Ti and 15-15Ti Steels
Fissolo A, Lévy V, Séran JL, Maillard A, Royer J, Rabouille O
Mechanical Property Degradation of Fast Reactor Fuel Cladding During Thermal Transients
Shibahara I, Omori T, Sato Y, Onose S, Nomura S
Fatigue Crack Growth Properties of Thermal Reactor Irradiated Nimonic PE16
Douglas JM, Gravenor JG
Influence of Cold Work on the Irradiation Creep and Creep Rupture of Titanium Modified Austenitic Stainless Steel
Garner FA, Hamilton ML, Eiholzer CR, Toloczko MB, Kumar AS
Mechanical Properties of 1950's Vintage Type 304 Stainless Steel Weldment Components After Low Temperature Neutron Irradiation
Sindelar RL, Caskey GR, Thomas JK, Hawthorne JR, Hiser AL, Lott RA, Begley JA, Shogan RP
Effects of Neutron Irradiations at Temperatures Below 500°C on the Properties of Cold Worked 316 Stainless Steels: A Review
Van Duysen JC, Todeschini P, Zacharie G
Technique to Eliminate Helium Induced Weld Cracking in Stainless Steels
Wang C-A, Grossbeck ML, Chin BA
Helium-Induced Weld Degradation of HT-9 Steel
Wang C-A, Lin HT, Grossbeck ML, Chin BA
The Complex Action of Major Solutes on Radiation-Induced Swelling of Fe-Cr-Ni Austenitic Alloys
Garner FA, Lauritzen T, Mitchell MA
Radiation Creep and Swelling of Austenitic 16Cr-15Ni-3Mo-Nb Steels Irradiated in the Reactor BOR-60 at 350 and 420 C
Neustroev VS, Shamardin VK
Swelling and Irradiation Creep of Neutron-Irradiated 316Ti and 15-15Ti Steels
Maillard A, Touron H, Séran J-L, Chalony A
Influence of Aluminum and Titanium on Gas Bubble Microstructure Formation in Nickel Under Helium-Ion Irradiation
Kalin BA, Chernov II, Kalashnikov AN, Markin AV, Shishkin GN, Korshunov SN
Stress Corrosion Cracking Susceptibility of Irradiated Type 304 Stainless Steels
Chung HM, Ruther WE, Sanecki JE, Hins AG, Kassner TF
Radiation-Induced Solute Segregation and Stress Corrosion Cracking Study of AISI 304 and AISI 304L Stainless Steels
Liu WJ, Kai JJ, Tsai CH
Influence of Impurities and Alloying Elements on IASCC in Neutron Irradiated Austenitic Stainless Steels
Kodama M, Fukuya K, Kayano H
The Relationship of Grain Boundary Composition in Irradiated Type 304SS to Neutron Fluence and IASCC
Jacobs AJ
Isotopic Tailoring with Ni to Study Helium Generation Rates and Their Effect on Tensile Properties of Neutron-Irradiated Fe-Cr-Ni Alloys
Garner FA, Hamilton ML, Greenwood LR, Stubbins JF, Oliver BM
Microstructural and Microchemical Evolution During Fast Neutron Irradiation in Nickel and Nickel-Silicon Alloys Doped with Isotopically Controlled Boron
Muroga T
The Effect of Phosphorus on the Microstructure of an Fe-16Cr-17Ni Austenitic Ternary Induced by Fast Neutron Irradiations
Watanabe H, Muroga T, Yoshida N
Void Formation and Induced-Segregation During Electron-Irradiation in Ti and Nb Modified Austenitic Steels
Ohnuki S, Takahashi H, Kinoshita H, Akasaka N, Onose S, Shibahara I
Effects of Applied Stress on Microstructural Evolution in 316SS Under Ion Irradiation
Katoh Y, Yutaka Y, Kohyama A
The Observation and Interpretation of Microstructural Evolution and Swelling in Austenitic Steels Under Irradiation
Sekimura N, Hamada K, Ishino S
Effects of Cascade Damage and Helium Production Under 600 MeV Proton Irradiation of Cu and Cu-AlO
Singh BN, Horsewell A
The Role of Nickel and Zinc in Defect Behavior and Microstructural Evolution of Copper Under Electron Irradiation
Muroga T, Ishimaru E, Yoshida N
Mechanical Properties of Induction Brazed Glidcop Al-15
Lee CK, Chin BA, Zinkle SJ, Wilcox RC
The Response of Dispersion-Strengthened Copper Alloys to High Fluence Neutron Irradiation at 415°C
Edwards DJ, Newkirk JW, Garner FA, Hamilton ML, Nadkarni A, Samal P
Effects of Hot Implantation of Helium in Copper on Bubble Formation Within Grains and on Grain Boundaries
Singh BN, Eldrup M, Möslang A
Evolution of Microstructure in Zirconium Alloy Core Components of Nuclear Reactors during Service
Griffiths M, Chow PCK, Coleman CE, Holt RA, Sagat S, Urbanic VF
Modelling the Effect of Texture and Dislocation Structure on Irradiation Creep of Zirconium Alloys
Christodoulou N, Causey AR, Woo CH, Tome CN, Klassen RJ, Holt RA
Strain Hardening Parameter Evaluation of Irradiated Zircaloy2
Balakrishnan KS, Chatterjee S
Irradiation Growth of Zirconium Alloys
Yang JC, Ren JY
The Effect of Irradiation on the Mechanical Properties of 6061-T651 Aluminum
Alexander DJ
Effects of High Thermal Neutron Fluences on Type 6061 Aluminum
Weeks JR, Czajkowski CJ, Farrell K
Irradiation-Induced Precipitation in Vanadium-Base Alloys Containing Titanium
Chung HM, Loomis BA, Smith DL
Fatigue Crack Growth of Neutron Irradiated V-15Cr-5Ti and V-3Ti-1Si
Witzenburg WV, de Bruyne HJ
Mechanical Properties of Vanadium Alloys Doped with Helium Using Various Techniques
Matsui H, Tanaka M, Yamamoto M, Hasegawa A, Abe K
Measurement of Electrical Conductivity of Ceramic Insulators in a Fission Reactor
Shikama T, Narui M, Kayano H, Sagawa T, Endo Y
Radiation Induced Mechanical Stresses in Polycrystalline Alumina Insulators
Wu WY, Chin BA, Zee RH
High-Temperature Irradiation of Alumina-Base Ceramic Materials in a Water Cooled Fission Reactor
Shikama T, Narui M, Kayano H, Sagawa T, Tanabe T, Fujitsuka M
The Effect of Neutron Irradiation on the Structure and Properties of Carbon-Carbon Composite Materials
Burchell TD, Eatherly WP, Strizak JP
Irradiation Behavior of Carbon-Boron-Titanium Materials
Tanabe T, Fujitsuka M, Shinno H, Shikama T
The Role of Phase-Boundary Fission-Gas Bubbles in the Cavitational Swelling of Irradiated U-Pu-Zr Fuel
Rest J
Effect of Neutron Irradiation on Thermal Conductivity of Carbon/Carbon Fiber Materials at 400 and 600°C in the Fluence Range 1 × 10 to 1 × 10 m
Thiele BA, Binkele L, Koizlik K, Nickel H
Author Index
Subject Index
Committee: E10
Paper ID: STP1175-EB
DOI: 10.1520/STP1175-EB
 ASTM International is a member of CrossRef.
0-8031-1488-5
978-0-8031-1488-3
STP1175-EB
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