DOE/ER-0313/17 - Volume 17
Semiannual Progress Report
September 30, 1994

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

1_IRRADIATION FACILITIES, TEST MATRICES, AND EXPERIMENTAL METHODS

1. Status of U.S./Japan Collaborative Program Phase II HFIR Target and RB* Capsules - J. E. Pawel, K. E. Lenox, A. W. Longest, R. L. Senn (Oak Ridge National Laboratory), and K. Shiba (Japan Atomic Energy Research Institute), pp. 3-7.
2. Vanadium Alloy Irradiation Experiment X530 in EBR-II - H. Tsai, R. V. Strain, A. G. Hins, H. M. Chung, L. J. Nowicki, and D. L. Smith (Argonne National Laboratory), pp. 8-14.

2_DOSIMETRY, DAMAGE PARAMETERS, TRANSMUTATION, AND ACTIVATION CALCULATIONS

1. Vanadium Irradiation at ATR - Neutronics Aspects - I. C. Gomes and D. L. Smith (Argonne National Laboratory), pp. 17-20.
2. Neutron Flux Spectra and Radiation Damage Parameters for the Russian BOR-60 and SM-2 Reactors - A. V. Karasiov (D. V. Efremov Scientific Research Institute of Electrophysical Apparatus, St. Petersburg, Russia) and L. R. Greenwood (Pacific Northwest Laboratory), pp.21-27.
3. Neutron Dosimetry, Damage Calculations, and Helium Measurements for the HFIR-MFE-60J-1 and MFE-330J-1 Spectral Tailoring Experiments - L. R. Greenwood (Pacific Northwest Laboratory), C. A. Baldwin (Oak Ridge National Laboratory), and B. M. Oliver (Rockwell International), pp. 28-34.
4. Preliminary Report on the Irradiation Conditions of the HFIR JP-23 Experiment - A. M. Ermi (Westinghouse Hanford Company) and D. S. Gelles (Pacific Northwest Laboratory), pp. 35-50.

3_FUNDAMENTAL MECHANICAL BEHAVIOR

1. Correlation Between Shear Punch and Tensile Data for Neutron-Irradiated Aluminum Alloys - M. L. Hamilton and D. J. Edwards (Pacific Northwest Laboratory), M. B. Toloczko and G. E. Lucas (University of California-Santa Barbara), W. F. Sommer and M. J. Borden (Los Alamos National Laboratory), and J. F. Dunlap and J. F. Stubbins (University of Illinois), pp. 55-66.

4_RADIATION EFFECTS, MECHANISTIC STUDIES, THEORY, AND MODELING

1. Comparison of Defect Cluster Accumulation and Pattern Formation in Irradiated Copper and Nickel - S. J. Zinkle and L. L. Snead (Oak Ridge National Laboratory), B. N. Singh (Riso National Laboratory), and D. J. Edwards (Pacific Northwest Laboratory), pp. 69-81.

5_FERRITIC MARTENSITIC AND BAINITIC STEELS

1. Effect of Internal Hydrogen on the Mixed-Mode I/III Fracture Toughness of a Ferritic/Martensitic Stainless Steel - H. Li (Associated Western Universities-Northwest Division, and D. S. Gelles (Pacific Northwest Laboratory), pp. 85-98.
2. Dependence of Mode I and Mixed Mode I/III Fracture Toughness on Temperature for a Ferritic/Martensitic Stainless Steel - H. Li (Associated Western Universities-Northwest Division), R. H. Jones (Pacific Northwest Laboratory), J. P. Hirth (Washington State University), and D. S. Gelles (Pacific Northwest Laboratory), pp. 99-109.
3. Embrittlement of Cr-Mo Steels After Low Fluence Irradiation in HFIR - R. L. Klueh and D. J. Alexander, pp. 110-121.

8_AUSTENITIC STAINLESS STEELS

1. Initial Tensile Test Results From J316 Stainless Steel Irradiated in the HFIR Spectrally Tailored Experiment - J. E. Pawel, M. L. Grossbeck, A. F. Rowcliffe (Oak Ridge National Laboratory) and K. Shiba (Japan Atomic Energy Research Institute), pp. 125-134.

9_REFRACTORY METAL ALLOYS

1. Chemical and Mechanical interactions of Interstitials in V-5%Cr-5%Ti - J. H. DeVan, J. R. DiStefano, J. W. Hendricks, and C. E. Matos (Oak Ridge National Laboratory), pp. 137-141.
2. Fatigue Behavior of Unirradiated V-5Cr-5Ti - B. G. Gieseke, C. O. Stevens, and M. L. Grossbeck (Oak Ridge National Laboratory), pp. 142-151.
3. Welding Development for V-Cr-Ti Alloys - J. F. King, G. M. Goodwin, and D. J. Alexander (Oak Ridge National Laboratory), pp. 152-155.
4. Dislocation Development in V-5Cr-5Ti and Pure Vanadium - D. S. Gelles (Pacific Northwest Laboratory) and M. L. Grossbeck (Oak Ridge National Laboratory), pp. 156-164.
5. Effect of Heat Treatment on Microstructure and Fracture Toughness of a V-5Cr-5Ti Alloy - H. Li (Associated Western Universities-Northwest Division), M. L. Hamilton and R. H. Jones (Pacific Northwest Laboratory), pp. 165-177.
6. Fabrication of 500-kg heat of V-4C4-4Ti - H. M. Chung, H.-C. Tsai, and D. L. Smith (Argonne National Laboratory) and R. Peterson, C. Curtis, C. Wojcik, and R. Kinney (Teledyne Wah Chang Albany), pp. 178-182.
7. Impact Properties of 500-kg Heat of V-4Cr-4Ti - H. M. Chung, L. Nowicki, J. Gazda, and D. L. Smith (Argonne National Laboratory), pp. 183-186.
8. Hardness Recovery of 85% Cold-Worked V-Ti and V-Cr-Ti Alloys Upon Annealing at 180°C to 1200°C - B. A. Loomis, L. J. Nowicki, and D. L. Smith (Argonne National Laboratory), pp. 187-193.
9. Effect of Oxidation of Tensile Behavior of V-5Cr-5Ti Alloy - K. Natesan and W. K. Soppet (Argonne National Laboratory), pp. 194-197.
10. Effect of Dynamically Charged Helium on Tensile Properties of V-4Cr-4Ti - H. M. Chung, B. A. Loomis, L. Nowicki, and D. L. Smith (Argonne National Laboratory), pp. 198-204.
11. Ductile-Brittle Transition Behavior of V-4Cr-4Ti- Irradiated in the Dynamic Helium Charging Experiment - H. M. Chung, L. J. Nowicki, D. E. Busch, and D. L. Smith (Argonne National Laboratory), pp. 205-210.
12. Void Structure and Density Change of Vanadium-Base Alloys Irradiated in the Dynamic Helium Charging Experiment - H. M. Chung, L. Nowicki, J. Gazda, and D. L. Smith (Argonne National Laboratory), pp. 211-218.

10_COPPER ALLOYS

1. Effect of Fission Neutron Irradiation on the Tensile and Electrical Properties of Copper and Copper Alloys
   S. A. Fabritsiev (D, V, Efremov Institute, St. Petersburg, Russia), A. S. Pokrovski (SRIAR, Dimitrovgrad, Russia), S. J. Zinkle (Oak Ridge National Laboratory), and D. J. Edwards (Pacific Northwest Laboratory), pp. 221-228.

11_ENVIRONMENTAL EFFECTS IN STRUCTURAL MATERIALS

1. Fabrication and Performance Testing of CaO Insulator Coatings on V-5%Cr-5%Ti in Liquid Lithium - J. H. Park, and G. Dragel (Argonne National Laboratory), pp. 231-244.
2. Fabrication of Aluminum Nitride and Its Stability in Liquid Alkali Metals - K. Natesan and D. L. Rink (Argonne National Laboratory), pp. 245-248.
3. Chemical Compatibility of Structural Materials in Alkali Metals - K. Natesan, D. L. Rink, R. Haglund, and R. W. Clark (Argonne National Laboratory), pp. 249-252.

12_SOLID BREEDING MATERIALS AND BERYLLIUM

1. An Investigation of the Desorption of Hydrogen from Lithium Oxide Using Temperature Programmed Desorption and Diffuse Reflectance Infrared Spectroscopy - J. P. Kopasz and C. E. Johnson (Argonne National Laboratory) and J. Ortiz-Villafuerte (Escuela Superior de Fisica y Matematics, Mexico), pp. 255-264.

13_CERAMICS

1. Fatigue Crack Growth Rate (FCGR) Behavior of Nicalon/SiC Composites - N. Miriyala, P. K. Liaw, N. Yu, and C. J. McHargue (University of Tennessee), L. L. Snead (Oak Ridge National Laboratory), and D. K. Hsu (Iowa State University), pp. 267-273.
2. Advanced SiC Composites for Fusion Applications - L. L. Snead and O. J. Schwarz (Oak Ridge National Laboratory), pp. 274-288.
3. Thermal Conductivity Degradation of Graphites Irradiated at Low Temperature - L. L. Snead and T. D. Burchell (Oak Ridge National Laboratory), pp. 289-295.
4. Incubation Time for Sub-Critical Crack Propagation in Sic-Sic Composites - A. El-Azab and N. M. Ghoniem (University of California, Los Angeles), pp. 296-310.
5. Apparent Activation Energy of Subcritical Crack Growth of SiC/SiC Composites at Elevated Temperatures - Y. S. Chou (Associated Western Universities, N.W.), N. M. Stackpoole and R. Bordia (University of Washington, Seattle), C. H. Henager, Jr., C. F> Windisch, Jr., and R. H. Jones (Pacific Northwest Laboratory), pp. 311-320.
6. Effects of Neutron Irradiation on Dimensional Stability and On Mechanical Properties of SiC/SiC Composites - G. E. Youngblood, G. H. Henager, Jr., D. J. Senor, and G. W. Hollenberg (Pacific Northwest Laboratory), pp. 321-330.
7. Effect of Irradiation Spectrum on the Microstructural Evolution in Ceramic Insulators - S. J. Zinkle (Oak Ridge National Laboratory), pp. 331-345.
8. Data Acquisition System Used in Radiation Induced Electrical Degradation Experiments - D. P. White (Oak Ridge National Laboratory), pp. 346-349.
9. Cation Disorder in High-Dose, Neutron-Irradiated Spinel - K. E. Sickafus, A. C. Larson, N. Yu, M. Nastasi (Los Alamos National Laboratory), G. W. Hollenberg and F. A. Garner (Pacific Northwest Laboratory), and R. C. Bradt (University of Nevada-Reno), pp. 350-361.
10. Elastic Stability of High Dose Neutron Irradiated Spinel - Z Li and S.-K. Chan (Argonne National Laboratory), F. A. Garner (Pacific Northwest Laboratory), and R. C. Bradt (University of Nevada-Reno), pp. 36-278.
11. Optical Absorption and Luminescence in Neutron-Irradiated, Silica-Based Fibers - D. W. Cooke, E. H. Farnum, F. W. Clinard, Jr., B. L. Bennett, B. Sundlof, and W. P. Unruh (Los Alamos National Laboratory), pp. 379-384.