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DOE/ER-0313/24 - Volume 24
Semiannual Progress Report
June 30, 1998

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1_VANADIUM ALLOYS

  1. Chemistry Related to the Procurement of Vanadium Alloys - D. L. Smith, H. M. Chung, and H. C. Tsai (Argonne National Laboratory), pp. 37.
  2. Production and Fabrication of Vanadium Alloys for the Radiative Divertor Program of DIII-D - W. R. Johnson and J. P. Smith (General Atomics), pp. 8-13.
  3. Revised ANL-Reported Tensile Data for V-Ti and V-Cr-Ti Alloys - M. C. Billone (Argonne National Laboratory), pp. 14-17.
  4. Tensile Properties of Vanadium Alloys Irradiated at 390°C in EBR-II - H. M. Chung, H.-C. Tsai, L. J. Nowicki, and D. L. Smith (Argonne National Laboratory), pp.18-21.
  5. Effect of Helium on Tensile Properties of Vanadium Alloys - H. M. Chung, M. C. Billone, and D. L. Smith (Argonne National Laboratory), pp. 22-28.
  6. Tensile Properties of Vanadium Alloys Irradiated at 200°C in the HFIR - H. M. Chung, L. Nowicki, and D. L. Smith (Argonne National Laboratory), pp. 29-32.
  7. Tensile Properties of Vanadium Alloys Irradiated at <430°C - H. M. Chung and D. L. Smith (Argonne National Laboratory), pp. 33-38.
  8. Microstructural Examination of V-(4-5%)Cr-4-5%)Ti Irradiated in X530 - D. S. Gelles (Pacific Northwest National Laboratory) and H. M. Chung (Argonne National Laboratory), pp. 39-46.
  9. Oxidation Kinetics and Microstructure of V-Cr-Ti Alloys Exposed to Oxygen-Containing Environments - K. Natesan (Argonne National Laboratory), M. Uz (Lafayette College, Easton, PA), and T. Ulie (Purdue University), pp. 47-49.
  10. Tensile Properties of Aluminized V-5Cr-5Ti Alloy After Exposure in Air Environment - K. Natesan and W. K. Soppet (Argonne National Laboratory), pp. 50-53.
  11. Heat Treatment Effects on Tensile Properties of V-(4-5) wt.% Cr-(4-5) wt.% Ti Alloys - K. Natesan and W. K. Sopper (Argonne National Laboratory), pp. 54-56.
  12. Study of Irradiation Creep of Vanadium Alloys - H. Tsai, R. V. Strain, and D. L. Smith (Argonne National Laboratory), and M. L. Grossbeck (Oak Ridge National Laboratory), pp. 57-60.
  13. Recent Progress on Gas Tungsten Arc Welding of Vanadium - M. L. Grossbeck, J. F. King, D. J. Alexander, and G. M. Goodwin (Oak Ridge National Laboratory), pp. 61-66.

2_SILICON CARBIDE COMPOSITE MATERIALS

  1. Investigation of Reactivity Between SiC and Nb-1Zr in Planned Irradiation Creep Experiments - C. A. Lewinsohn (Associated Western Universities), M. L. Hamilton, and R. H. Jones (Pacific Northwest National Laboratory), pp. 69-74.
  2. Analysis of Neutron Irradiation Effects on Thermal Conductivity of SiC-Based Composites and Monolithic Ceramics - G. E. Youngblood and D. J. Senor (Pacific Northwest National Laboratory), pp. 75-80.
  3. Creep Behavior for Advanced Polycrystalline 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 Advance Energy, Kyoto University, Japan), pp. 81-86.
  4. Design of a Creep Experiment for SiC/SiC Composites in HFIR - S. L. Hecht (Duke Engineering Hanford), M. L. Hamilton, R. H. Jones, G. E. Youngblood, and R. A. Schwartz (Pacific Northwest National Laboratory), and C. A. Lewinsohn (Associated Western Universities), pp. 87-110.
  5. Thermomechanical Instability Effects in SiC-Based Fibers and SiC/SiC Composites - G. E. Youngblood, C. H. Henager, and R. H. Jones (Pacific Northwest National Laboratory), pp. 111-118.

3_FERRITIC/MARTENSITIC STEELS

  1. Heat Treatment Effects on Impact Toughness of 9Cr-1MoVNb and 12Cr-1MoVW Steels Irradiated to 100 dpa - R. L. Klueh and D. J. Alexander (Oak Ridge National Laboratory), pp. 121-128.
  2. Neutron Irradiation Effects on the Ductile-Brittle Transition of Ferritic/Martensitic Steels - R. L. Klueh and D. J. Alexander (Oak Ridge National Laboratory), p. 129.
  3. Microstructural Characterization of 5-9% Chromium Reduced-Activation Steels - R. Jayaram (University of Pittsburgh) and R. L. Klueh (Oak Ridge National Laboratory), pp. 130-140.

4_COPPER ALLOYS AND HIGH HEAT FLUX MATERIALS

  1. Effect of Heat Treatments on the Tensile and Electrical Properties of High-Strenght, High-Conductivity Copper Alloys - S. J. Zinkle and W. S. Eatherly (Oak Ridge National Laboratory), pp. 143-148.
  2. Investigation of the Influence of Grain Boundary Chemistry, Test Temperature, and Strain Rate on the Fracture Behavior of ITER Copper Alloys - K. Leedy and J. F. Stubbins (University of Illinois), D. J. Edwards (Pacific Northwest National Laboratory), R. R. Solomon (OMG Americas), and D. Kurs (Brush Wellman), pp. 149-156.

5_AUSTENITIC STAINLESS STEELS

  1. Microstructural Evolution of Austenitic Stainless Steels Irradiated to 17 dpa in Spectrally Tailored Experiment of the ORR and HFIR at 400°C - E. Wakai (Japan Atomic Energy Research Institute), N. Hashimoto (Oak Ridge National Laboratory), T. Sawai (JAERI), J. P. Robertson and L. T. Gibson (Oak Ridge National Laboratory), I. Ioka and A. Hishinuma (JAERI), pp. 159-168.
  2. The Development of a Tensile-Shear Punch Correlation for Yield Properties of Model Austenitic Alloys - G. L. Hankin (IPTME, Loughborough University), M. L. Hamilton and F. A. Garner (Pacific Northwest National Laboratory), and R. G. Faulkner (IPTME, Loughborough University), pp. 169-176.

6_INSULATING CERAMICS AND OPTICAL MATERIALS

  1. Summary of the 9th IEA Workshop on Radiation Effects in Ceramic Insulators - S. J. Zinkle (Oak Ridge National Laboratory), E. R. Hodgson (CIEMAT), and T. Shikama (Tohoku University), pp. 179-187.
  2. Analysis of In-Situ Electrical Conductivity Data from the HFIR TRIST-ER1 Experiment - S. J. Zinkle, L. L. Snead, and W. S. Eatherly (Oak Ridge National Laboratory), E. H. Farnum (Los Alamos National Laboratory), T. Shikama (Tohoku University), and K. Shiiyama (Kyusha University), pp. 188-203.
  3. Irradiation Spectrum and Ionization-Induced Diffusion Effects in Ceramics - S. J. Zinkle (Oak Ridge National Laboratory), pp. 204-210.
  4. Defect Production in Ceramics - S. J. Zinkle (Oak Ridge National Laboratory) and C. Konoshita (Kyusha University), pp. 211-212.

7_RADIATION EFFECTS, MECHANISTIC STUDIES, AND EXPERIMENTAL METHODS

  1. Effects of In-Cascade Clustering on Near-Term Defect Evolution - H. L. Heinisch (Pacific Northwest National Laboratory), pp. 217-220.
  2. Influence of Subcascade Formation on Displacement Damage at High PKA Energies - R. E. Stollar (Oak Ridge National Laboratory) and L. R. Greenwood (Pacific Northwest National Laboratory), pp. 221-224.

8_DOSIMETRY, DAMAGE PARAMETERS, AND ACTIVATION CALCULATIONS

  1. Analysis of the DHCE Experiment in the Position A10 of the ATR Reactor - I. C. Gomes, D. L. Smith, and H. Tsai (Argonne National Laboratory), pp. 227-231.
  2. Neutronics Analysis of the DHCE Experiment in ATR-ITV - I. C. Gomes, D. L. Smith, and H. Tsai (Argonne National Laboratory), pp. 232-238.

9_IRRADIATION FACILITIES, TEST MATRICES, AND EXPERIMENTAL METHODS

  1. Progress Report on the Varying Temperature Experiment - A. L. Qualls, M. T. Hurst, D. G. Raby, D. W. Sparks (Oak Ridge National Laboratory), and T. Muroga (National Institute for Fusion Science), pp. 243-253.
  2. The Monbusho/U.S. Shielded HFIR Irradiation Experiment: HFIR-MFE-RB-11J and 12J (P3-2 and P3-3) - M. L. Grossbeck and K. E. Lenox (Oak Ridge National Laboratory) and T. Muroga (National Institute for Fusion Science), pp. 254-283.
  3. Neutron Irradiation of V-Cr-Ti Alloys in the BOR-60 Fast Reactor: Description of the Fusion-1 Experiment - A. F. Rowcliffe (Oak Ridge National Laboratory), H. C. Tsai and D. L. Smith (Argonne Natinal Laboratory), and V. kazakov, and V. Chakin (RIAR, Dimitrovgrad), pp. 284-299.
  4. Design Considerations of the Irradiation Test Vehicle for the Advanced Test Reactor - H. Tsai, C. Gomes, and D. L. Smith (Argonne National Laboratory), A. J. Palmer, S. J. Hafer, and F. W. Ingram (Lockheed Martin Idaho Technologies Company), M. L. Hamilton (Pacific Northwest National Laboratory), K. R. Thoms (Oak Ridge National Laboratory), and F. W. Wiffen (U.S. Department of Energy), pp. 300-302.
  5. Status of ATR-A1 Irradiation Experiment on Vanadium Alloys and Low-Activation Steels - H. Tsai, R. V. Strain, I. Gomes, and D. L. Smith (Argonne National Laboratory), L. R. Greenwood (Pacific Northwest National Laboratory), and H. Matsui (Tohoku University, Japan), pp. 303-326.
  6. Schedule and Status of Irradiation Experiments - A. F. Rowcliffe, M. L. Grossbeck, and J. P. Robertson (Oak Ridge National Laboratory), pp. 327-.
   

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