DOE/ER-0313/21 - Volume 21
Semiannual Progress Report
December 31, 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 P. W. Trester (General Atomics), pp. 3-9.
2. Performance of V-4Cr-4Ti Material Exposed to DIII-D Tokamak Environment - H. Tsai, H. M. Chung, and D. L. Smith (Argonne National Laboratory), W. R. Johnson and J. P. Smith (General Atomics), pp. 10-14.
3. Electrical Resistivity of V-Cr-Ti Alloys - S. J. Zinkle, A. N. Gubbi, and W. S. Eatherly (Oak Ridge National Laboratory), pp. 15-19.
4. Dynamic Finite Element Analysis of Third Size Charpy Specimens of V-4Cr-4Ti - M. R. Lansberry (University of Missouri-Rollo), R. J. Kurtz (Pacific Northwest National Laboratory), A. S. Kumar (University of Missouri-Rolla), and G. E. Mueller (University of Missouri-Rolla), pp. 20-26.
5. Mode I and Mixed Move I/III Crack Initiation and Propagation Behavior of V-4Cr-4Ti Alloy at 25°C - H.-X. (Huaxin) Li, R. J. Kurtz and R. H. Jones (Pacific Northwest National Laboratory), pp. 27-30.
6. An Evaluation of the Susceptibility of V-4Cr-4Ti to Stress Corrosion Cracking in Room Temperature DIII-D Water - R. J. Kurtz (Pacific Northwest National Laboratory), W. R. Johnson (General Atomics Company), and R. H. Jones (Pacific Northwest National Laboratory), pp. 31-35.
7. Tensile Properties of V-5Cr-5Ti Alloys After Exposure in Air Environment - K. Natesan and W. K. Soppet (Argonne National Laboratory), pp. 36-39.
8. Tensile Properties of V-Cr-Ti Alloys after Exposure in Helium and Low-Partial Pressure Oxygen Environments - K. natesan and W. K. Soppet (Argonne National Laboratory), pp. 40-44.
9. Measurement of Hydrogen Solubility and Desorption Rate in V-4Cr-4Ti and Liquid Lithium-Calcium Alloys - H.-H. Park, R. Erck, E.-T. Park, S. Crossley, and F. Deleglise (Argonne National Laboratory), pp. 45-51.
10. Evaluating Electrically Insulating Films Deposited on V-4%Cr-4%Ti by Reactive CVD - J.-H. Park and W. D. Cho (Argonne National Laboratory), pp. 52-56.
11. Recent Progress on Gas Tungsten Arc Welding of Vanadium Alloys - J. F. King, M. L. Grossbeck, G. M. Goodwin, and D. J. Alexander (Oak Ridge National Laboratory), pp. 57-61.
12. Studies on the Effects of Helium on the Microstructural Evolution of V-3.8Cr-3.9Ti - N. Doraiswamy, B. Kestel, and D. E. Alexander (Argonne National Laboratory), p. 62.
13. Assessment of the Radiation-Induced Loss of Ductility in V-Cr-Ti Alloys - A. F. Rowcliffe and S. J. Zinkle (Oak Ridge National Laboratory), p. 63-72.
14. Effect of Fast Neutron Irradiation to 4 dpa at 400°C on the Properties of V-(4-5)Cr-(4-5)Ti Alloys - S. J. Zinkle, D. J. Alexander, J. P. Robertson, L. L. Snead, A. F. Rowcliffe, L. T. Gibson, W. S. Eatherly (Oak Ridge National Laboratory) and H. Tsai (Argonne National Laboratory), pp. 73-78.
15. Microstructural Examination of Irradiated Vanadium Alloys - D. S. Gelles (Pacific Northwest National Laboratory) and H. M. Chung (Argonne National Laboratory), pp. 79-84.

3_SILICON CARBIDE COMPOSITE MATERIALS

1. High Thermal Conductivity SiC/SiC Composites for Fusion Applications - J. C. Withers, W. Kowbel, and R. O. Loutfy (MER Corp.), G. E. Youngblood (Pacific Northwest National Laboratory), and C. Wong (General Atomics), pp. 87-88.
2. Creep Behavior for Advanced Polycrstalline SiC Fibers - G. E. Youngblood and R. H. Jones (Pacific Northwest National Laboratory), G. N. Morscher (Case Western Reserve University), and Akira Kohyama (Institute of Advanced Energy, Kyoto University, Kyoto 611, Japan), pp. 89-93.
3. Thermogravimetric and Microscopic Analysis of SiC/SiC Materials with Advanced Interfaces - J. F. Windisch, Jr., R. H. Jones (Pacific Northwest National Laboratory), and L. L. Snead (Oak Ridge National Laboratory), pp. 94-98.
4. Threshold Irradiation Dose for Amorphization of Silicon Carbide - L. L. Snead and S. J. Zinkle (Oak Ridge National Laboratory), pp. 99-110.
5. Stored Energy in Irradiated Silicon Carbide - L. L. Snead and T. D. Burchell (Oak Ridge National Laboratory), pp. 111-116 .
6. Effects of Neutron Irradiation on the Strength of Continuous Fiber Reinforced SiC/SiC Composites - G. E. Youngblood, C. H. Henager, Jr., and R. H. Jones (Pacific Northwest National Laboratory), pp. 117-123.
7. The Monotonic and Fatigue Behavior of CFCCs at Ambient Temperature and 1000°C - N. Miriyala, P. K. Liaw, and C. J. McHargue (University of Tennessee), and L. L. Snead (Oak Ridge National Laboratory), pp. 124-134.

4_FERRITIC/MARTENSITIC STEELS

1. Development of Oxide Dispersion Strengthened Ferritic Steels for Fusion - D. K. Mukhopadhyay, C. Suryanarayana, F. H. Froes (University of Idaho), and D. S. Gelles (Pacific Northwest National Laboratory), pp. 137-141.
2. Fracture Toughness of the IEA Heat of F82H Ferritic/Martensitic Stainless Steel as a Function of Loading Mode - Huaxin Li, D. S. Gelles (Pacific Northwest National Laboratory), J. P. Hirth (Washington State University-Pullman), and R. H. Jones (Pacific Northwest National Laboratory), pp. 142-146.
3. Summary of the IEA Workshop/Working Group Meeting on Ferritic/Martensitic Steels for Fusion - R. L. Klueh (Oak Ridge National Laboratory), pp. 147-150.
4. Further Charpy Impact Test Results of Low Activation Ferritic Alloys Irradiated at 430°C to 67 dpa - L. E. Schubert, M. L. Hamilton, and D. S. Gelles (Pacific Northwest National Laboratory).
5. The Effect of Fusion-Relevant Helium Levels on the Mechanical Properties of Isotopically Tailored Ferritic Alloys - G. L. Hankin (IPTME), M. L. Hamilton, D. S. Gelles (Pacific Northwest National Laboratory), and M. B. Toloczko (Washington State University), pp. 156-161.
6. Irradiation Creep of Various Ferritic Alloys Irradiated at -400°C in the PFR and FFTF Reactors - M. B. Toloczko and F. A. Garner (Pacific Northwest National Laboratory), and C. R. Eiholzer (Westinghouse Hanford Company), p. 162.

5_COPPER ALLOYS AND HIGH HEAT FLUX MATERIALS

1. Effect of Test Temperature and Strain Rate on the Tensile Properties of High-Strength, High-Conductivity Copper Alloys - S. J. Zinkle and W. S. Eatherly (Oak Ridge National Laboratory), pp. 165-174.
2. Fracture Toughness of Copper-Base Alloys for ITER Applications: A Preliminary Report - D. J. Alexander, S. J. Zinkle, and A. F. Rowcliffe (Oak Ridge National Laboratory), pp. 175-182.
3. Recent Results on the Neutron Irradiation of ITER Candidate Copper Alloys Irradiated in DR-3 at 250°C to 0.3 dpa - D. J. Edwards (PNNL), B. N. Singh, P. Toft, and M. Eldrup (Riso National Laboratory), pp. 183-193.
4. Irradiation Creep of Dispersion Strengthened Copper Alloy - A. S. Pokrovski, V. R. Barabash, S. A. Fabritisiev, M. L. Hamilton, C. R. Eiholzer, F. A. Garner, and D. J. Edwards, p. 194.

6_AUSTENITIC STAINLESS STEELS

1. Extreme Embrittlement of Austenitic Stainless Steel Irradiated to 75-81 dpa at 335-360°C - S. I. Porollo, A. N. Vorobjev, and Yu V. Konobeev (Institute of Physics and Power Engineering, Obninsk, Kaluga Region, Russia) and F. A. Garner (Pacific Northwest National Laboratory, p. 197.
2. The Independence of Irradiation Creep in Austenitic Alloys of Displacement Rate and Helium to dpa Ratio - F. A. Garner and m. B. Toloczko (Pacific Northwest National Laboratory) and M. L. Grossbeck (Oak Ridge National Laboratory), p. 198.
3. The Compositional Dependence of Irradiation Creep of Austenitic Alloys Irradiated in PFR at 420°C - M. B. Toloczko and F. A. Garner (Pacific Northwest National Laboratory), J. STandring (UKAEA, United Kingdom, retired), B. Munro and S. Adaway (AEA Technology, Dounreay, Scotland), p. 199.
4. Irradiation Creep and Stress-Enhanced Swelling of Fe-16Cr-15Ni-Nb Austenitic Stainless Steel in BN-350 - A. N. Vorobjev, Yu V. Konobeev, and S. I. Porollo (Institute of Physics and Power Engineering, Obninsk, Russia), N. I. Budylkin and E. G. Mironova (Bochvar's Research Institute for Nonorganic Materials, Moscow, Russia), and F. A. Garner (Pacific Northwest Naitonal Laboratory), p. 200.

7_RADIATION EFFECTS, MECHANISTIC STUDIES, AND EXPERIMENTAL METHODS

1. Atomic Scale Modeling of Defect Production and Microstructure Evolution in Irradiated Metals - T. Diaz de la Rubia, N. Soneda, E. Alons, K. Morishita, and Y. Shimomura, pp. 207-213.
2. Stochastic Annealing Simulations of Defect Interactions Among Subcascades - H. L. Heinisch (Pacific Northwest Naitonal Laboratory) and B. N. Singh (Riso National Laboratory), pp. 214-217.
3. The Effects of Self-Interstitial Clusters on Cascade Defect Evolution Beyond the Primary Damage State - H. l. Heinisch (Pacific Northwest National Laboratory), pp. 218-222.

8_DOSIMETRY, DAMAGE PARAMETERS, AND ACTIVATION CALCULATIONS

1. Neutron Dosimetry and Damage Calculations for the EBRII Cobra-1A Irradiations - L. R. Greenwood and R. T. Ratner (Pacific Northwest National Laboratory), pp. 225-228.
2. Neutron Dosimetry and Damage Calculations for the HFIR-JP-23 Irradiations - L. R. Greenwood (Pacific Northwest National Laboratory) and R. T. Ratner (Pacific Northwest National Laboratory), pp. 229-232.
3. The Dependence of Helium Generation Rate on Nickel Content of Fe-Cr-Ni Alloys Irradiated at High Dpa Levels in Fast Reactors - F. A. Garner, B. M. oliver, and L. R. Greenwood (Pacific Northwest National Laboratory), p. 233.

9_MATERIALS ENGINEERING AND DESIGN REQUIREMENTS

1. Impurity Content of Reduced-Activiation Ferritic Steels and a Vanadium Alloy - R. L. Klueh, M. L. Grossbeck, and E. E. Bloom (Oak Ridge National Laboratory), pp. 237-246.

10_IRRADIATION FACILITIES, TEST MATRICES, AND EXPERIMENTAL METHODS

1. Status of DOE/JAERI Collaborative Program Phase II and Phase III Capsules - J. E. Pawel, K. E, Lenox (Oak Ridge National Laboratory), and I. Ioka (Japan Atomic Energy Research Institute), pp. 312-313.
2. Status of Irradiation Experiment on Vanadium Alloys and Low-Activation Steels - H. Tsai, R. V. Strain, I. Gomes, H. Chung, and D. L. Smith (Argonne National Laboratory), and H. Matsui (Tohoku Univesity), pp. 314-320.
3. Progress Report on the Design of a Varying Temperature Irradiation Experiment for Operation in HFIR - A. L. Qualls (Oak Ridge National Laboratory) and T. Muroga (National Institute for Fusion Science), pp. 255-262.
4. Disassembly of the Fusion-1 Capsule after Irradiation in the BOR-60 Reactor - H. Tsai (Argonne National Laboratory), V. A. Kazakov and V. P. Chakin (Research Institute of Atomic Reactors), and A. F. Rowcliffe (Oak Ridge National Laboratory), pp. 263-264.
5. Schedule and Status of Irradiation Experiments - A. F. Rowcliffe and M. L. Grossbeck (Oak Ridge National Laboratory), pp. 265-274.