DOE/ER-0313/20 - Volume 20
Semiannual Progress Report
June 30, 1996

• Full Text (PDF)*
• Table of Contents with Summaries (PDF)

1_VANADIUM ALLOYS

1. Production and Fabrication of Vanadium Alloys for the Radiative Divertor Program of DIII-D - W. R. Johnson, J. P. Smith, and R. D. Stambaugh (General Atomics), pp. 3-10.
2. A Master Curve-Mechanism Based Approach to Modeling the Effects of Constraint, Loading Rate and Irradiation on the Toughness-Temperature Behavior of V-4Cr-4Ti Alloy - G. R. Odette, E. Donahue, G. E. Lucas, and J. W. Scheckherd (University of California, Santa Barbara), pp. 11-29.
3. Fracture Toughness Testing of V-4Cr-4Ti at 25°C and -196°C - H-X Li and R. J. Kurtz (Pacific Northwest National Laboratory), pp. 30-35.
4. Effect of Time and Temperature on Grain Size of V and V-Cr-Ti Alloys - K. Natesan and D. L. Rink (Argonne National Laboratory), pp. 36-37.
5. Effects of Strain Rate, Test Temperature, and Test Environment on Tensile Properites of Vanadium Alloys - A. N. Gubbi, A. F. Rowcliffe, W. S. Eatherly, and L. T. Gibson (Oak Ridge National Laboratory), pp. 38-52.
6. Development of Laser Welding Techniques for Vanadium Alloys - R. V. Strain, K. H. Leong, and D. L. Smith (Argonne National Laboratory), pp. 53-54.
7. Impact Properties and Hardening Behavior of Laser and Electron-Beam Welds of V-4Cr-4Ti - H. M. Chung, R. V. Strain, H-C. Tsai, J-H. Park, and D. L. Smith (Argonne National Laboratory), pp. 55-58.
8. Microstructural Characteristics and Mechanism of Toughness Improvement of Laser and Electron-Beam Welds of V-4Cr-4Ti Following Postwelding Heat-Treatment - H. M. Chung, J-H. Park, J. Gazda, and D. L. Smith (Argonne National Laboratory), pp. 59-66.
9. Evaluation of Flow Properties in the Weldments of Vanadium Alloys Using a Novel Indentation Technique - A. N. Gubbi, A. F. Rowcliffe, W. S. Eatherly, and L. T. Gibson (Oak Ridge National Laboratory), pp. 67-77.
10. Properties of V-(8-9)Cr-(5-6)Ti Alloys Irradiated in the Dynamic Helium Charging Experiment - H. M. chung, L. Nowicki, and D. L. Smith (Argonne National Laboratory), pp. 78-83.
11. Tensile Properties of V-(4-15)-Cr-5Ti Alloys Irradiated at 400°C in the HFIR - H. M. Chung, L. Nowicki, and D. L. Smith (Argonne National Laboratory), pp. 84-86.
12. Effects of Irradiation at Low Temperature on V-4Cr-4Ti - D. J. Alexander, L. L. Snead, S. J. Zinkle, A. N. Gubbi, A. F. Rowcliffe, and E. E. Bloom (Oak Ridge National Laboratory), pp. 87-95.
13. Grain Boundary Migration Induced Segregation in V-Cr-Ti Alloy - D. S. Gelles (Pacific Northwest National Laboratory) and S. Ohnuki and H. Takahashi (University of Hokkaido), pp. 96-99.
14. Helium Effects on Irradiation Damage in V Alloys - N. Doraiswamy and D. Alexander (Argonne National Laboratory), pp. 100-102.
15. Study on In-Reactor Creep of Vanadium Alloy in the HFIR RB-12J Experiment - R. V. Strian, C. F. Konicek, and H. Tsai (Argonne National Laboratory), pp. 103-104.
16. Oxidation Kinetics and Microstructure of V-(4-5) WT.%Cr-(4-5) WT.5ti Alloys Exposed to Air at 300-650°C - K. Natesan (Argonne National Laboratory) and M. Uz (Lafayette College), pp. 105-110.
17. CaO Insulator Coatings on a Vanadium-Base Alloy in Liquid 2 at % Calcium-Lithium - J.-H. park and T. F. Kassner (Argonne National Laboratory), pp. 111-118.

2_SILICON CARBIDE COMPOSITE MATERIALS

1. Revised Activation Estimates for Silicon Carbide - H. L. Heinisch (Pacific Northwest National Laboratory), E. T. Cheng (TSI Research), and F. M. Mann (Westinghouse Hanford Company), pp. 121-123.
2. Time-Dependent Bridging and Life Prediction of SiC/SiC in a Hypothetical Fusion Environment - C. H. Henegar, Jr., C. A. Lewinshon, C. F. Windisch, Jr., and R. H. Jones (Pacific Northwest National Laboratory), pp. 124-129.
3. The Cyclic Fatigue Behavior of a Nicalon/SiC Composite - N. Miriyala, P. K. Liaw, and C. J. McHargue (University of Tennessee) and L. L. Snead (Oak Ridge National Laboratory), pp. 130-135.
4. Neutron Irradiation Effects on High Nicalon Silicon Carbide Fibers - M. C. Osborne, D. Steiner (Rensselser Polytechnic Institute) and L. L. Snead (Oak Ridge National Laboratory), pp. 136-139.
5. Specimen Size Effect Considerations for Irradiation Studies of SiC/SiC - G. E. Youngblood, C. H. Henegar, Jr., and R. H. Jones (Pacific Northwest National Laboratory), pp. 140-145.
6. Technique for Measuring Irradiation Creep in Polycrystalline SiC Fibers - G. E. Youngblood, M. L. Hamilton, and R. H. Jones (Pacific Northwest National Laboratory), pp. 146-151
7. Progress in the Development of a SiCCf/SiC Creep Test - M. L. Hamilton, C. A. Lewinsohn, R. H. Jones, G. E. Youngblood, and F. A. Garner (Pacific Northwest National Laboratory) and S. L. Hecht (Westinghouse Hanford Company), pp. 152-158.

3_FERRITIC/MARTENSITIC STEELS

1. Tensile and Charpy Impact Properties of Irradiated Reduced-Activation Ferritic Steels - R. L. Klueh and D. J. Alexander (Oak Ridge National Laboratory), pp. 161-170.
2. Charpy Impact Test Results of Four Low Activation Ferritic Alloys Irradiated at 370°C to 15 DPA - L. E. Schubert, M. L. Hamilton, and D. S. Gelles (Pacific Northwest National Laboratory), pp. 171-176.
3. Fractographic Examination of Reduced Activation Ferritic/Martensitic Steel Charpy Speciments Irradiated to 30 DPA at 370°C - D. S. Gelles and M. L. Hamilton (Pacific Northwest National Laboratory) and L. E. Schubert (University of Missouri, Rolla), pp. 177-182.
4. Low-Chromium Reduced-Activation Chromium-Tungsten Steels - R. L. Klueh, D. J. Alexander, and P. J. Maziasz (Oak Ridge National Laboratory), pp. 183-188.
5. Heat-To-Heat Variability of Irradiation Creep and Swelling of HT9 Irradiated to High Neutron Fluence at 400-600°C - M. B. Toloczko and F. A. Garner (Pacific Northwest National Laboratory), p. 189.
6. Preliminary Results of the Round-Robin Testing of F82H - K. Shiba and N. Yamanouchi (Japan Atomic Energy Reserach Institute) and A. Tohyama (Nippon Kohkan Co.), pp. 190-194.
7. Mechanical Properties and Microstructure of F-82H Welded Joints Using CO2 Laser Beam - N. Yamanouchi and K. Shiba (Japan Atomic Energy Research Institute), pp. 195-198.
8. The Consequences of Helium Production on Microstructural Development in Isotopically Tailored Ferritic Alloys - D. S. Gelles (Pacific Northwest National Laboratory), pp. 199-204.

4_COPPER ALLOYS AND HIGH HEAT FLUX MATERIALS

1. Tensile and Electrical Properties of Unirradiated and Irradiated Hycon 3HPtm CuNiBe - S. J. Zinkle and W. S. Eatherly (Oak Ridge National Laboratory), pp. 207-216.
2. Fracture Toughness of Oxide-Dispersion Strengthened Copper - D. J. Alexander (Oak Ridge National Laboratory), pp. 217-220.
3. Effects of Bonding Bakeout Thermal Cycles on Pre- and Postirradiation Microstructures, Physical, and Mechanical Properties of Copper Alloys - B. N. Singh, M. Eldrup, and P. Toft (Riso National Laboratory) and D. J. Edwards (Pacific Northwest National Laboratory), p. 221.
4. Influence of Nickel and Beryllium Content on Swelling Behavior of Copper Irradiated with Fast Neutrons - B. N. Singh (Riso National Laboratory), F. A. Garner and D. J. Edwards (Pacific Northwest National Laboratory), and J. H. Evans (University of London), p. 222.

5_AUSTENITIC STAINLESS STEELS

1. Temperature Dependence of the Deformation Behavior of 316 Stainless Steel After Low Temperature Neutron Irradiation - J. E. Pawel-Robertson (Oak Ridge National Laboratory), I. Ioka (Japan Atomic Energy Research Institute), A. F. Rowcliffe, M. L. Grossbeck (Oak Ridge National Laboratory), and S. Jitsukawa (Japan Atomic Energy Research Institute), pp. 225-238.
2. Tensile Properties of a Titanium Modified Austenitic Stainless Steel and the Weld Joints After Neutron Irradiation - K. Shiba, I. Ioka, S. Jitsukawa, S. Hamada, A. Hishinuma (Japan Atomic Energy Research Institute), and J. Pawel-Robertson (Oak Ridge National Laboratory), pp. 239-250.
3. Irradiation Creep and Swelling of Various Austenitic Alloys Irradiated in PFR and FFTF - F. A. Garner and M. B. Toloczko (Pacific Northwest National Laboratory), B. Munro and S. Adaway (AEA Technology, and J. Standring (UKAEA, retired), p. 251.
4. Radiation-Induced Instability of MnS Precipitates and its Possible Consequences on IASCC of Austentic Stainless Steels - H. M. Chung (Argonne National Laboratory), and F. A. Garner (Pacific Northwest National Laboratory), p. 252.
5. Tensile Behavior of Irradiated Manganese-Stabilized Stainless Steel - R. L. Klueh (Oak Ridge National Laboratory), pp. 253-254.

6_INSULATING CERAMICS AND OPTICAL MATERIALS

1. In-Situ Measurement of the Electrical Conductivity of Aluminum Oxide in HFIR - S. J. Zinkle, D. P. White, L. L. Snead, W. S. Eatherly, A. L. Qualls, D. W. Heatherly, R. G. Sitterson, R. L. Wallace, D. G. Raby and M. T. Hurst (Oak Ridge National Laboratory), E. H. Parnum and K. Scarborough (Los Alamos National Laboratory), T. Shikama and M. Narui (Tohoku University), and K. Shiiyama (Kyushu University), pp. 247-266.
2. Summary of the Irradiation History of the Trist-ERI Capsule - A. L. Qualls, W. S. Eatherly, D. W. Heatherly, M. T. Hurst, D. G. Raby, R. G. Stitterson, L. L. Snead, K. R. Thoms, R. L. Wallace, and S. J. Zinkle (Oak Ridge National Laboratory), pp. 267-271.
3. Summary of Round Robin Measurements of Radiation Induced Conducitivity in Wesgo AL995 Alumina - S. J. Zinkle (Oak Ridge National Laboratory), pp. 272-274.
4. Optical Absorption of Neutron-Irradiated Silica Fibers - D. W. Cooke, E. H. Farnum, and B. L. Bennett (Los Alamos National Laboratory), pp. 275-278.

7_RADIATION EFFECTS, MECHANISTIC STUDIES, AND EXPERIMENTAL METHODS

1. An Integrated Approach to Assessing the Fracture Safe Margins of Fusion Reactor Structures - G. R. Odette (University of California, Santa Barbara), pp. 283-298.
2. Defect Interactions Within a Group of Subcascades - H. L. Heinisch (Pacific Northwest National Laboratory), pp. 299-302.

8_DOSIMETRY, DAMAGE PARAMETERS, AND ACTIVATION CALCULATIONS

1. Neutron Dosimetry and Damage Calculations for the HFIR-JP-23 Irradiations - L. R. Greenwood and R. T. Ratner (Pacific Northwest National Laboratory), pp. 305-308.
2. A Revaluation of Helium/DPA Ratios for Fast Reactor and Thermal Reactor Data in Fission-Fusion Correlations - F. A. Garner and L. R. Greenwood (Pacific Northwest National Laboratory), and B. M. Oliver (Rockwell International Corporation), pp. 309-310.

9_IRRADIATION FACILITIES, TEST MATRICES, AND EXPERIMENTAL METHODS

1. Status of ATR-A1 Irradiation Experiment of Vanadium Alloys and Low-Activation Steels - H. Tsai, R. V. Strain, I. Gomes, and D. L. Smith (Argonne National Laboratory) and H. Matsui (Tohoku University, Japan), pp. 315-318.
2. Feasibility of Conducting a Dynamic Helium Charging Experiment for Vanadium Alloys in the Advanced Test Reactor - H. Tsai, I. Gomes, R. V. Strain, and D. L. Smith (Argonne National Laboratory), and H. Matsui (Tohoku University), pp. 319-322.
3. Schedule and Status of Irradiation Experiments - A. F. Rowcliffe and M. L. Grossbeck (Oak Ridge National Laboratory), pp. 323-332.