DOE/ER-0313/23 - Volume 23
Semiannual Progress Report
December 31, 1997

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

1_VANADIUM ALLOYS

1. Revised ANL-Reported Tensile Data for Unirradiated and Irradiated (FFTF, HFIR) V-Ti and V-Cr-Ti Alloys - M. C. Billone (Argonne National Laboratory), pp. 3-61.
2. Impact Properties of Vanadium-Base Alloys Irradiated at <430°C - H. M. Chung and D. L. Smith (Argonne National Laboratory), pp. 62-69.
3. Tensile and Impact Properties of Vanadium-Base Alloys Irradiated at Low Temperatures in the ATR-A1 Experiment - H. Tsai, L. J. Nowicki, M. C. Billone, H. M. Chung, and D. L. Smith (Argonne National Laboratory), pp. 70-76.
4. Strain Rate Dependence of the Tensile Properties of V-(4-5%) Cr-(4-5%) Ti Irradiated in EBR-II and HFBR - S. J. Zinkle, L. L. Snead, J. P. Robertson, and A. F. Rowcliffe (Oak Ridge National Laboratory), pp. 77-80.
5. Summary of the Investigation of Low Temperature, Low Dose Radiation Effects on the V-4Cr-4Ti Alloy - L. L. Snead, S. J. Zinkle, D. J. Alexander, A. F. Rowcliffe, J. P. Robertson, and W. S. Eatherly (Oak Ridge National Laboratory), pp. 81-98.
6. Thermophysical and Mechanical Properties of V-(4-5)%Cr-(4-5)%Ti Alloys - S. J. Zinkle (Oak Ridge National Laboratory (pp. 99-108.
7. Effect of Thickness and Loading Mode on the Fracture Properties of V-4Cr-4Ti at Room Temperature - H. Li, J. Kurtz, and R. H. Jones (Pacific Northwest National Laboratory), pp. 109-110.
8. Grain Boundary Chemistry and Heat Treatment Effects on the Ductile-To-Brittle Transition Behavior of Vanadium Alloys - R. J. Kurtz, M. L. Hamilton, and H. Li (Pacific Northwest National Laboratory), pp. 111-118.
9. Temperature Dependence of the Radiation Damage Microstructure in V-4Cr-4Ti Neutron Irradiated to Low Dose - P. M. Rice and S. J. Zinkle (Oak Ridge National Laboratory), p. 119.
10. Microstructural Examination of Irradiated V-(4-5%)Cr-(4-5%)Ti - D. S. Gelles (Pacific Northwest National Laboratory), P. M. Rice and S. J. Zinkle (Oak Ridge National Laboratory), and H. M. Chung (Argonne National Laboratory), p. 120.
11. Microstructure of V-Cr-4Ti Alloy After Low-Temperature Irradiation by Ions and Neutrons - J. Gazda and M. Meshii (Northwestern University), and H. M. Chung (Argonne National Laboratory), pp. 121-125.
12. Research and Development on Vanadium Alloys for Fusion Applications - S. J. Zinkle (Oak Ridge National Laboratory), H. Matsui (Tohoku University), D. L. Smith (Argonne National Laboratory), A. F. Rowcliffe (Oak Ridge National Laboratory), E. van Osch (NERF-Petten), K. Abe (Tohoku University), and V. A. Kazakov (RIAR-Dimitrovgrad), p. 126.
13. Tensile Properties of V-Cr-Ti Alloys After Exposure in Hydrogen-Containing Environments - K. Natesan and W. K. Soppet (Argonne National Laboratory), pp. 127-129.
14. Tensile Properties of V-Cr-Ti Alloys After Exposure in Oxygen-Containing Environments - K. Natesan and W. K. Soppett (Argonne National Laboratory), pp. 130-135.
15. Laser-Welded V-Cr-Ti Alloys: Microstructural and Mechanical Properties - K. Natesan, D. L. Smith, P. G. Sanders, and K. H. Leong (Argonne National Laboratory), pp. 136-140.
16. Performance of V-4Cr-4Ti Material Exposed to the DIII-D Tokamak Environment - H. Tsai, D. L. Smith, H. M. Chung (Argonne National Laboratory), W. R. Johnson and J. P. Smith (General Atomics), and W. R. Wampler (Sandia National Laboratory), pp. 141-148.
17. Irradiation Creep of Vanadium-Base Alloys - H. Tsai, M. Billone, R. V. Strain, and D. L. Smith (Argonne National Laboratory), and H. Matsui (Tohoku University), pp. 149-156.
18. Procurement of V-Cr-Ti Alloys to Study Minor Variations on V-4Cr-4Ti - M. L. Grossbeck (Oak Ridge National Laboratory), pp. 157-160.

2_SILICON CARBIDE COMPOSITE MATERIALS

1. Radiation Response of SiC-Based Fibers - G. E. Youngblood and R. H. Jones (Pacific Northwest National Laboratory), Akira Kohyama (Institute of Advanced Energy, Kyoto, Japan), and L. L. Snead (Oak Ridge National Laboratory), pp. 163-165.
2. Methods of Radiation Effects Evaluation of SiC/SiC Composite and SiC Fibers - G. E. Youngblood and R. H. Jones (Pacific Northwest National Laboratory), pp. 166-170.
3. Fiber Creep Rate and High-Temperature Properties of SiC/SiC Composites - C. A. Lewinsohn, R. H. Jones, G. E. Youngblood, and C. H. Henager, Jr. (Pacific Northwest National Laboratory), p. 171.
4. High Thermal Conductivity SiC/SiC Composites for Fusion Applications-II - W. Kowbel, K. T. Tsou, and J. C. Withers (MER Corporation, Tucson, AZ), and G. E. Youngblood (Pacific Northwest National Laboratory), pp. 172-174.
5. Minimum Bar Size for Flexure Testing of Irradiated SiC/SiC Composite - G. E. Youngblood and R. H. Jones (Pacific Northwest National Laboratory), pp. 175-176.

3_FERRITIC/MARTENSITIC STEELS

1. Radiation Hardening and Deformation Behavior of Irradiated Ferritic-Martensitic Steels - J. P. Robertson, R. L. Klueh (Oak Ridge National Laboratory), K. Shiba (Japan Atomic Energy Research Institute), and A. F. Rowcliffe (Oak Ridge National Laboratory), pp. 179-187.
2. A Reassessment of the Effects of Helium on Charpy Impact Properties of Ferritic/Martensitic Steels - D. S. Gelles and M. L. Hamilton (Pacific Northwest National Laboratory), and G. L. Hankin (Longborough University, England), p. 188.
3. Development of Oxide Dispersion Strengthened Ferritic Steels for Fusion - D. K. Mukhopadhyay (Vista Metlas, Inc., McKessport, PA), F. H. Froes (University of Idaho), and D. S. Gelles (Pacific Northwest National Laboratory), p. 189.
4. Microstructural Evolution of HFIR-Irradiated Low Activation F82H and F82H-10B Steels - E. Wakai (Japan Atomic Energy Research Institute), N. Hashimoto (Oak Ridge National Laboratory), K. Shiba, T. Sawai (JAERI), J. P. Robertson, R. L. Klueh, A. F. Rowcliffe (Oak Ridge National Laboratory), and A. Hishinuma (JAERI), pp. 190-197.
5. Effect of Heat Treatment and Irradiation Temperature on Impact Behavior of Irradiated Reduced-Activation Ferritic Steels - R. L. Klueh and D. J. Alexander (Oak Ridge National Laboratory), pp. 198-209.
6. Irradiation Creep of Various Ferritic Alloys Irradiated at -400°C in the PFR and FFTF Reactors - M. B. Toloczko (Washington State University), F. A. Garner (Pacific Northwest National Laboratory), and C. R. Eiholer (Westinghouse Hanford Company), p. 210.

4_COPPER ALLOYS AND HIGH HEAT FLUX MATERIALS

1. Temperature and Strain Rate Effects in High Strength High Conductivity Copper Alloys Tested in Air - D. J. Edwards (Pacific Northwest National Laboratory), p. 213-222.
2. The Effect of Bonding and Bakeout Thermal Cycles on the Properties of Copper Alloys Irradiated at 100°C - D. J. Edwards (Pacific Northwest National Laboratory), B. N. Singh, P. Toft, and M. Eldrup (Riso National Laboratory), pp. 223-225.
3. Effect of Initial Oxygen Content on the Void Swelling Behavior of Fast Neutron Irradiated Copper - S. J. Zinkle (Oak Ridge National Laboratory) and F. A. Garner (Pacific Northwest National Laboratory), pp. 226-228.

5_AUSTENITIC STAINLESS STEELS

1. The Dependence of Irradiation Creep in Austenitic Alloys on Displacement Rate and Helium to DPA Ratio - F. A. Garner (Pacific Northwest National Laboratory), M. B. Toloczko (Washington State University), and M. L. Grossbeck (Oak Ridge National Laboratory), p. 231.
2. Extreme Embrittlement of Austenitic Stainless Steel Irradiated to 75-81 DPA at 335-360°C - S. I. Porollo, A. N. Vorobjev, Yu. V. Konobeev (Institute of Physics and Power Engineering, Obninsk, Kaluga Region, Russia), and F. A. Garner (Pacific Northwest National Laboratory), p. 232.
3. Shear Punch Testing of 59Ni Isotopically-Doped Model Austenitic Alloys After Irradiation in FFTF at Different He/DPA Ratios - G. L. Hanken and R. G. Faulkner (IPTME, Loughborough University, Leicestershire, LE113UT, UK) and M. L. Hamilton and F. A. Garner (Pacific Northwest National Laboratory), p. 233.
4. Damage Structure of Austenitic Stainless Steel 316LN Irradiated at Low Temperature in HFIR - N. Hashimoto (Oak Ridge National Laboratory), E. Wakai (Japan Atomic Energy Research Institute), J. P. Robertson, M. L. Grossbeck, and A. F. Rowcliffe (Oak Ridge National Laboratory), pp. 234-242.

6_SOLID BREEDING MATERIALS

1. Postirradiation Examination of Beryllium Pebbles - D. S. Gelles (Pacific Northwest Naitonal Laboratory), pp. 247-253.
2. Neutron Irradiation of Beryllium Pebbles - D. S. Gelles, H. Tsai, and R. M. Ermi (Pacific Northwest Naitonal Laboratory), and (Argonne National Laboratory), pp. 254-258.
3. Stepped-Anneal Helium Release in 1-MM Beryllium Pebbles from Cobra 1A2 - B. M. Oliver (Pacific Northwest National Laboratory), pp. 259-266.
4. Thermal Ramp Tritium Release in Cobra-1A2 C03 Beryllium Pebbles - D. L. Baldwin (Pacific Northwest National Laboratory), pp. 267-271.
5. Helium Analyses of 1-MM Beryllium Microspheres from Cobra-1A2 - B. M. Oliver (Pacific Northwest National Laboratory), pp. 272-278.
6. Tritium Analyses of Cobra-1A2 Beryllium Pebbles - D. L. Baldwin (Pacific Northwest National Laboratory), pp. 279-288.

7_RADIATION EFFECTS, MECHANISTIC STUDIES, AND EXPERIMENTAL METHODS

• Fundamental Radiation Effects Parameters in Metals and Ceramics - S. J. Zinkle (Oak Ridge National Laboratory, p. 291.
• Validation of the Shear Punch-Tensile Correlation Technique Using Irradiated Materials - G. L. Hankin and R. G. Faulkner (IPTME, Loughborough University, Leicestershire, LE11 3UT, UK), M. B. Toloczko (Washington State University), and M. L. Hamilton (Pacific Northwest National Laboratory), p. 292.
• Subcascade Formation in Displacement Cascade Simulation: Implications for Fusion Reactor Materials - Roger E. Stollar (Oak Ridge National Laboratory) and Lawrence R. Greenwood (Pacific Northwest National Laboratory),pp. 293-295.
• Stochastic Annealing Simulation of Copper Under Continuous Neutron Irradiation - H. L. Heinisch (Pacific Northwest National Laboratory) and B. N. Singh (Riso National Laboratory), pp. 296-297.
• Contribution to Irradiation Creep Arising from Gas-Driven Bubble Growth - C. H. Woo (The Hong Kong Polytechnic University, Kowloon, Hong Kong), and F. A. Garner (Pacific Northwest National Laboratory), p. 298.

8_DOSIMETRY, DAMAGE PARAMETERS, AND ACTIVATION CALCULATIONS

1. Neutron Dosimetry and Damage Calculations for the HFIR-JP-9 -12, and -15 Irradiations - L. R. Greenwood (Pacific Northwest National Laboratory) and C. A. Baldwin (Oak Ridge National Laboratory), pp. 301-304.
2. Neutron Dosimetry and Damage Calculations for the HFIR-JP-20 Irradiation - L. R. Greenwood (Pacific Northwest National Laboratory) and C. A. Baldwin (Oak Ridge National Laboratory), pp. 305-308.
3. Neutron Dosimetry and Radiation Damage Calculations for NFBR - L. R. Greenwood and R. T. Ratner (Pacific Northwest National Laboratory), pp. 309-316.
4. Production of 4HE and Tritium from BE in the Cobra-1A2-I Irradiation - L. R. Greenwood (Pacific Northwest National Laboratory), pp. 317-322.
5. Production of 4HE, 3HE, and Tritium from BE Irradiated in FFTF-MOTA-2B - L. R. Greenwood (Pacific Northwest National Laboratory), pp. 323-327.
6. Calculation and Measurement of Helium Generation and Solid Transmutants in Cu-Zn-Ni Alloys - L. R. Greenwood, B. M. Oliver, and F. A. Garner (Pacific Northwest National Laboratory), and T. Muroga (National Institute of Fusion Science, Nagoya 464-01, Japan), p. 328.
7. Neutron Dosimetry and Damage Calculations for the HFIR-MFE-200J-1 Irradiation "A corrected version of this contribution was posted February 23, 2006" - L. R. Greenwood (Pacific Northwest National Laboratory) and C. A. Baldwin (Oak Ridge National Laboratory), pp. 329-332.
8. Neutronics Aspects of a DHCE Experiment - I. C. Gomes, H. Tsai, and D. L. Smith (Argonne National Laboratory), pp. 333-342.

9_IRRADIATION FACILITIES, TEST MATRICES, AND EXPERIMENTAL METHODS

1. Description and Status of the U.S./JAERI HFIR-MFE-RB-10J Irradiation Capsule - J. P. Robertson, K. E. Lenox, M. L. Grossbeck, and A. F. Rowcliffe (Oak Ridge National Laboratory), and S. Jitsukawa and K. Shiba (Japan Atomic Energy Research Institute), pp. 345-346.
2. Summary of the U.S. Specimen Matrix for the HFIR 13J Varying Temperature Irradiation Capsule - S. J. Zinkle (Oak Ridge National Laboratory), pp., 352-355.
3. Schedule and Status of Irradiation Experiments - A. F. Rowcliffe, M. L. Grossbeck, and J. P. Robertson (Oak Ridge National Laboratory), pp. 356-.