STP1175

    Effects of Radiation on Materials: 16th International Symposium

    Kumar AE, Gelles DS, Nanstad RK, Little TA

    Pages: 7

    Published: 1994

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    Comprehensive look at the latest research on how radiation effects metal and non-metal materials, with emphasis on fundamental mechanisms of damage and applications to nuclear systems.

    Over 80 peer-review papers in 15 sections. The diversity of the selections cover a complete range of topics, including:

    • The importance of research on radiation embrittlement as a predictor of safety margins

    • General aspects of radiation damage

    • Research covering reactor pressure vessels (RPV) steels and the various properties and microstructures

    • Results of studies of ferritic and ferritic-martensitic steels

    • Areas of research involving austentic alloys, copper and copper alloys, as well as alloys of zirconium, aluminum and vanadium

    • Irradiation of nonmetallics, including one paper on fast reactor nuclear fuel.


    Table of Contents

    Meeting Future Power Needs in Licensing Space
    Rossin A.

    Usnrc Research on Reactor Pressure Vessel Steel Embrittlement
    Mayfield M., Taboada A.

    Irradiation Creep due to SIPA Under Cascade Damage Conditions
    Garner F., Holt R., Woo C.

    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 R., Little E.

    Segregation Effects in Ferritic Fe-Cr Alloys
    Gelles D.

    Neutron Irradiation Damage and Hardness Anisotropy in Molybdenum Single Crystals
    Abe K., Arai K., Kanzaki M., Satou M.

    Strengthening of Chromium Films by 75 Mev Ni Ion Irradiation
    Jain A., Jaipal ., Kanjilal D., Loganathan S., Mehta G.

    Radiation Damage Rate Measurements in Nickel
    Schüle W.

    Effects of Fission and Fusion Neutron Irradiations on Mechanical Properties and Defect Recovery Behavior in α-Iron
    Aono Y., Kayano H., Kuramoto E., Kurishita H., Yoshida N.

    Subsize Specimen Testing of a Nuclear Reactor Pressure Vessel Material
    Cannon N., Hamilton M., Kumar A., Rosinski S.

    The Effect of Loading Rate Upon Irradiation Embrittlement Measured by Fracture Mechanical Properties
    Ahlstrand R., Rintamaa R., Valo M., Wallin K.

    Effects Of Irradiation Temperature on Embrittlement of Nuclear Pressure Vessel Steels
    Haggag F.

    Study on the Irradiation Embrittlement of a Microalloyed Ferritic Steel
    Balakrishnan K., Ganguly C., Viswanathan U.

    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 H., Viswanathan U.

    Development and Application of an LWR Reactor Pressure Vessel-Specific Flaw Distribution
    Foulds J., Kennedy E., Rosinski S.

    Effects of Irradiation Temperature on Charpy and Tensile Properties of High-Copper, Low Upper-Shelf, Submerged-Arc Welds
    Berggren R., Nanstad R.

    Evaluation of Thermal-Aged Plates, Forgings, and Submerged-Arc Weld Metals
    DeVan M., Lowe A., Wade C.

    Effect of Specimen Size on the Impact Properties of a Pressure Vessel Weld Material
    Cannon N., Hamilton M., Kumar A.

    Further Microstructural Characterization of Submerged-Arc Weld Metals - II
    Lawless K., Lowe A.

    Exploratory Studies of the Effects of Irradiation Temperature on Mechanical Properties of Structural Steels amd Welds
    Hawthorne J.

    The Radiation Hardening and Embrittlement of a Mild Steel Submerged-Arc Weld
    Bischler P., Bolton C., Buswell J., Jones L., Jones R., Phythian W., Sinclair R., Wootton M.

    Annealing Experiments on Irradiated NiCrMo Weld Metal
    Hofmann G., Klausnitzer E., Leitz C.

    Degradation of Mechanical Properties of Stainless Steel Cladding Due to Neutron Irradiation and Thermal Aging
    Haggag F.

    The Effect of Flux on the Irradiation Hardening of Pressure Vessel Steels
    English C., Lucas G., Mader E., Odette G., Phythian W.

    Modeling the Influence of Irradiation Temperature and Displacement Rate on Hardening Due to Point Defect Clusters in Ferritic Steels
    Stoller R.

    The Modelling of Radiation Hardening and Embrittlement in Magnox Mild Steel Submerged-Arc Welds
    Buswell J., Jones R.

    Irradiation Induced Precipitation in Model Alloys with Systematic Variation of Cu, Ni and P Content: A Small Angle Neutron Scattering Study
    Frisius F., Solt G., Tipping P., Waeber W.

    Characterisation of Model Fe-Cu-Mn-Ti-N Alloys by Electron Microscopy and Positron Annihilation
    de Diego N., Mace J., McElroy R., Phythian W.

    An APFIM Survey of Grain Boundary Segregation and Precipitation in Irradiated Pressure Vessel Steels
    Burke M., Miller M.

    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 J., Zacharie G.

    Metallurgical Considerations in the Application of DPA to Reactor Vessel Analysis
    Harbison L., Lowe A.

    Postirradiation Deformation Behavior in Ferritic Fe-Cr Alloys
    Gardner P., Gelles D., Hamilton M.

    Tensile and Fracture Mechanics Properties of Neutron Irradiated Manet I (Martensitic 11Cr Steel Type DIN 1.4914)
    de Vries M.

    Influence of Cold Work, Heat Treatment, and Chromium Content on the Fracture Properties of Irradiated Martensitic Steels
    Huang F.

    Charpy Impact Toughness of Martensitic Steels Irradiated in FFTF: Effect of Heat Treatment
    Alexander D., Klueh R.

    Microstructural Studies in Fast Reactor Irradiated FV448 Ferritic-Martensitic Alloy Plate and Weldment
    Faulkner R., Little E., Morgan T.

    Effects of Neutron Irradiation on the Notch Ductility of 15MnTi Steel
    Aixin Y., Han R.

    The Influence of Specimen Size on Measurement of Thermal or Irradiation Creep in Pressurized Tubes
    Duncan D., Eiholzer C., Garner F., Hamilton M., Kumar A., Puigh R., Toloczko M.

    Tensile Properties of Neutron Irradiated 316Ti and 15-15Ti Steels
    Fissolo A., Lévy V., Maillard A., Rabouille O., Royer J., Séran J.

    Mechanical Property Degradation of Fast Reactor Fuel Cladding During Thermal Transients
    Nomura S., Omori T., Onose S., Sato Y., Shibahara I.

    Fatigue Crack Growth Properties of Thermal Reactor Irradiated Nimonic PE16
    Douglas J., Gravenor J.

    Influence of Cold Work on the Irradiation Creep and Creep Rupture of Titanium Modified Austenitic Stainless Steel
    Eiholzer C., Garner F., Hamilton M., Kumar A., Toloczko M.

    Mechanical Properties of 1950's Vintage Type 304 Stainless Steel Weldment Components After Low Temperature Neutron Irradiation
    Begley J., Caskey G., Hawthorne J., Hiser A., Lott R., Shogan R., Sindelar R., Thomas J.

    Effects of Neutron Irradiations at Temperatures Below 500°C on the Properties of Cold Worked 316 Stainless Steels: A Review
    Todeschini P., Van Duysen J., Zacharie G.

    Technique to Eliminate Helium Induced Weld Cracking in Stainless Steels
    Chin B., Grossbeck M., Wang C.

    Helium-Induced Weld Degradation of HT-9 Steel
    Chin B., Grossbeck M., Lin H., Wang C.

    The Complex Action of Major Solutes on Radiation-Induced Swelling of Fe-Cr-Ni Austenitic Alloys
    Garner F., Lauritzen T., Mitchell M.

    Radiation Creep and Swelling of Austenitic 16Cr-15Ni-3Mo-Nb Steels Irradiated in the Reactor BOR-60 at 350 and 420 C
    Neustroev V., Shamardin V.

    Swelling and Irradiation Creep of Neutron-Irradiated 316Ti and 15-15Ti Steels
    Chalony A., Maillard A., Séran J., Touron H.

    Influence of Aluminum and Titanium on Gas Bubble Microstructure Formation in Nickel Under Helium-Ion Irradiation
    Chernov I., Kalashnikov A., Kalin B., Korshunov S., Markin A., Shishkin G.

    Stress Corrosion Cracking Susceptibility of Irradiated Type 304 Stainless Steels
    Chung H., Hins A., Kassner T., Ruther W., Sanecki J.

    Radiation-Induced Solute Segregation and Stress Corrosion Cracking Study of AISI 304 and AISI 304L Stainless Steels
    Kai J., Liu W., Tsai C.

    Influence of Impurities and Alloying Elements on IASCC in Neutron Irradiated Austenitic Stainless Steels
    Fukuya K., Kayano H., Kodama M.

    The Relationship of Grain Boundary Composition in Irradiated Type 304SS to Neutron Fluence and IASCC
    Jacobs A.

    Isotopic Tailoring with 59Ni to Study Helium Generation Rates and Their Effect on Tensile Properties of Neutron-Irradiated Fe-Cr-Ni Alloys
    Garner F., Greenwood L., Hamilton M., Oliver B., Stubbins J.

    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
    Muroga T., Watanabe H., Yoshida N.

    Void Formation and Induced-Segregation During Electron-Irradiation in Ti and Nb Modified Austenitic Steels
    Akasaka N., Kinoshita H., Ohnuki S., Onose S., Shibahara I., Takahashi H.

    Effects of Applied Stress on Microstructural Evolution in 316SS Under Ion Irradiation
    Katoh Y., Kohyama A., Yutaka Y.

    The Observation and Interpretation of Microstructural Evolution and Swelling in Austenitic Steels Under Irradiation
    Hamada K., Ishino S., Sekimura N.

    Effects of Cascade Damage and Helium Production Under 600 MeV Proton Irradiation of Cu and Cu-Al2O3
    Horsewell A., Singh B.

    The Role of Nickel and Zinc in Defect Behavior and Microstructural Evolution of Copper Under Electron Irradiation
    Ishimaru E., Muroga T., Yoshida N.

    Mechanical Properties of Induction Brazed Glidcop Al-15
    Chin B., Lee C., Wilcox R., Zinkle S.

    The Response of Dispersion-Strengthened Copper Alloys to High Fluence Neutron Irradiation at 415°C
    Edwards D., Garner F., Hamilton M., Nadkarni A., Newkirk J., Samal P.

    Effects of Hot Implantation of Helium in Copper on Bubble Formation Within Grains and on Grain Boundaries
    Eldrup M., Möslang A., Singh B.

    Evolution of Microstructure in Zirconium Alloy Core Components of Nuclear Reactors during Service
    Chow P., Coleman C., Griffiths M., Holt R., Sagat S., Urbanic V.

    Modelling the Effect of Texture and Dislocation Structure on Irradiation Creep of Zirconium Alloys
    Causey A., Christodoulou N., Holt R., Klassen R., Tome C., Woo C.

    Strain Hardening Parameter Evaluation of Irradiated Zircaloy—2
    Balakrishnan K., Chatterjee S.

    Irradiation Growth of Zirconium Alloys
    Ren J., Yang J.

    The Effect of Irradiation on the Mechanical Properties of 6061-T651 Aluminum
    Alexander D.

    Effects of High Thermal Neutron Fluences on Type 6061 Aluminum
    Czajkowski C., Farrell K., Weeks J.

    Irradiation-Induced Precipitation in Vanadium-Base Alloys Containing Titanium
    Chung H., Loomis B., Smith D.

    Fatigue Crack Growth of Neutron Irradiated V-15Cr-5Ti and V-3Ti-1Si
    de Bruyne H., Witzenburg W.

    Mechanical Properties of Vanadium Alloys Doped with Helium Using Various Techniques
    Abe K., Hasegawa A., Matsui H., Tanaka M., Yamamoto M.

    Measurement of Electrical Conductivity of Ceramic Insulators in a Fission Reactor
    Endo Y., Kayano H., Narui M., Sagawa T., Shikama T.

    Radiation Induced Mechanical Stresses in Polycrystalline Alumina Insulators
    Chin B., Wu W., Zee R.

    High-Temperature Irradiation of Alumina-Base Ceramic Materials in a Water Cooled Fission Reactor
    Fujitsuka M., Kayano H., Narui M., Sagawa T., Shikama T., Tanabe T.

    The Effect of Neutron Irradiation on the Structure and Properties of Carbon-Carbon Composite Materials
    Burchell T., Eatherly W., Strizak J.

    Irradiation Behavior of Carbon-Boron-Titanium Materials
    Fujitsuka M., Shikama T., Shinno H., Tanabe 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 × 1022 to 1 × 1024 m-2
    Binkele L., Koizlik K., Nickel H., Thiele B.

    Author Index

    Subject Index


    Committee: E10

    Paper ID: STP1175-EB

    DOI: 10.1520/STP1175-EB

    ISBN-EB: 978-0-8031-5262-5

    ISBN-PRINT: 978-0-8031-1488-3

    ASTM International is a member of CrossRef.

    0-8031-1488-5
    978-0-8031-1488-3
    STP1175-EB