DOE/ER-0313/35 - Volume 35
Semiannual Progress Report
December 31, 2003

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

1_VANADIUM ALLOYS

1. FABRICATION OF CREEP TUBING FROM THE US AND NIFS HEATS OF V-4Cr-4Ti—A. F. Rowcliffe, D. T. Hoelzer, and M. L. Grossbeck (Oak Ridge National Laboratory), pp. 2-11.

2_CERAMIC COMPOSITE MATERIALS

1. COMPATIBILITY OF CVD SIC WITH PB-LI AT 800°-1100°C—B. A. Pint, L. D. Chitwood, and J. R. DiStefano (Oak Ridge National Laboratory, USA), pp. 13-17.
2. EFFECTS OF IRRADIATION AND POST IRRADIATION ANNEALING ON THE THERMAL CONDUCTIVITY/ DIFFUSIVITY OF MONOLITHIC SIC AND SIC/SIC COMPOSITES—G. E. Youngblood, D. J. Senor, and R. H. Jones (Pacific Northwest National Laboratory)*, pp. 18-19.
3. MODELING THE TRANSVERSE THERMAL CONDUCTIVITY OF 2D-SICF/SIC COMPOSITES MADE WITH WOVEN FABRIC—G. E. Youngblood, D. J. Senor, and R. H. Jones (Pacific Northwest National Laboratory)*, pp. 20-21.
4. A MODEL STRESS ANALYSIS OF SWELLING IN SIC/SIC COMPOSITES AS A FUNCTION OF FIBER TYPE AND CARBON INTERPHASE STRUCTURE—C. H. Henager, Jr. (Pacific Northwest National Laboratory), E. A. Le (University of Washington), and R. H. Jones (Pacific Northwest National Laboratory)*, pp. 22.
5. HELIUM EFFECT ON IRRADIATED MICROSTRUCTURES AND PROPERTIES IN SiC/SiC COMPOSITES—Y. Katoh (Oak Ridge National Laboratory), S. Kondo, K. Ozawa, K. H. Park, and A. Kohyama (Kyoto University), pp. 23-27.
6. SiC/SiC COMPOSITES THROUGH TRANSIENT EUTECTIC-PHASE ROUTE FOR FUSION APPLICATIONS—Y. Katoh (Oak Ridge National Laboratory), A. Kohyama, T. Nozawa (Kyoto University), and M. Sato (Ube Industries, Ltd.), pp. 28.

3_FERRITIC/MARTENSITIC STEELS

1. ANALYSIS OF EXTRACTION RESIDUE OF HFIR 11J-IRRADIATED RAFS—H. Tanigawa (Japan Atomic Energy Research Institute), H. Sakasegawa (Kyoto University), S. J. Zinkle, R. L. Klueh (Oak Ridge National Laboratory), and A. Kohyama (Kyoto University), pp. 30-32.
2. ANALYSIS OF Ta-RICH MX PRECIPITATES IN RAFS—H. Tanigawa (Japan Atomic Energy Research Institute), H. Sakasegawa (Kyoto University), N. Hashimoto, S. J. Zinkle, and R. L. Klueh (Oak Ridge National Laboratory), and A. Kohyama (Kyoto University), pp. 33-36.
3. X-RAY DIFFRACTION ANALYSIS ON PRECIPITATES OF 11J IRRADIATED RAFS—H. Tanigawa (Japan Atomic Energy Research Institute), H. Sakasegawa (Kyoto University), E. A. Payzant, S. J. Zinkle, and R. L. Klueh (Oak Ridge National Laboratory), and A. Kohyama (Kyoto University), pp. 37-40.
4. COMPARISON OF MICROSTRUCTURE BETWEEN NEUTRON-IRRADIATED REDUCEDACTIVATION FERRITIC/MARTENSITIC STEELS, F82H-IEA, JLF-1 AND ORNL9CR—N. Hashimoto (Oak Ridge National Laboratory), H. Tanigawa (Japan Atomic Energy Research Institute), M. Ando (JAERI), T. Sawai (JAERI), K. Shiba (JAERI), and R.L. Klueh (ORNL), pp. 41-44.
5. UPDATE ON FRACTURE TOUGHNESS VARIABILITY IN F82H—D. S. Gelles (Pacific Northwest National Laboratory)* and Mikhail A. Sokolov (Oak Ridge National Laboratory), pp. 45-50.
6. A MASTER CURVE ANALYSIS OF F82H USING STATISTICAL AND CONSTRAINT LOSS SIZE ADJUSTMENTS OF SMALL SPECIMEN DATA—G. R. Odette, T. Yamamoto, H. Kishimoto, W. J. Yang, and G. E. Lucas (University of California, Santa Barbara), M. Sokolov (Oak Ridge National Laboratory), P. Spätig (CRPP EPFL, Switzerland), and J.-W. Rensman (NRG Petten, The Netherlands), pp. 51-57.
7. ON THE EFFECTS OF FATIGUE PRECRACKING ON THE MICROSTRUCTURE AROUND PRECRACK IN 1TCT FRACTURE TOUGHNESS SPECIMEN OF F82H-IEA—H. Tanigawa (Japan Atomic Energy Research Institute), N. Hashimoto, M. A. Sokolov, and R. L. Klueh (Oak Ridge National Laboratory), and M. Ando (JAERI), pp. 58-66.
8. TEM OBSERVATION AROUND CRACK IN FATIGUE-PRECRACKED 1TCT FRACTURE TOUGHNESS SPECIMEN OF F82H-IEA—N. Hashimoto (Oak Ridge National Laboratory), H. Tanigawa (Japan Atomic Energy Research Institute), M. Ando (JAERI), and M. A. Sokolov (ORNL), pp. 67-70.
9. IRRADIATION CREEP AND SWELLING FROM 400°C TO 600°C OF THE OXIDE DISPERSION STRENGTHENED FERRITIC ALLOY MA957—M. B. Toloczko, D. S. Gelles, F. A. Garner, and R. J. Kurtz (Pacific Northwest National Laboratory),* and K. Abe (Dept. of Quantum Sci. and Energy Eng., Tohoku University, Sendai, Japan), pp. 71-72.
10. IRRADIATION EFFECTS ON TENSILE PROPERTIES OF HIGH-CHROMIUM FERRITIC/MARTENSITIC STEELS–R. L. Klueh (Oak Ridge National Laboratory), pp. 73-79.
11. AN ANALYSIS OF THE EFFECTS OF HELIUM ON FAST FRACTURE AND EMBRITTLEMENT OF ª 8Cr TEMPERED MARTENSITIC STEELS—G. R. Odette, T. Yamamoto, and H. Kishimoto (University of California, Santa Barbara), pp. 80-90.
12. INFLUENCE OF HIGH DOSE NEUTRON IRRADIATION ON MICROSTRUCTURE OF EP-450 FERRITIC MARTENSITIC STEEL IRRADIATED IN THREE RUSSIAN FAST REACTORS—A. M. Dvoriashin, S. I. Porollo, and Yu. V. Konobeev (Institute of Physics and Power Engineering), and F. A.Garner (Pacific Northwest National Laboratory)*, pp. 91-99.
13. COMPILATION AND PRELIMINARY ANALYSIS OF A IRRADIATION HARDENING AND EMBRITTLEMENT DATABASE FOR 8Cr MARTENSITIC STEELS–T. Yamamoto, G. R. Odette, H. Kishimoto (University of California, Santa Barbara), and J. W. Rensman (NRG, Petten), pp. 100-114.
14. EXTRAPOLATION OF FRACTURE TOUGHNESS DATA FOR HT9 IRRADIATED AT TEMPERATURES 360 390°C—R. J. Kurtz and D. S. Gelles (Pacific Northwest National Laboratory)*, pp. 115-128.
15. NANOFEATURE DEVELOPMENT AND STABILITY IN NANOSTRUCTURED FERRITIC ALLOYS— M. J. Alinger and G. R. Odette (University of California, Santa Barbara) and D. T. Hoelzer (Oak Ridge National Laboratory), pp. 129-134.

4_COPPER ALLOYS

1. EVOLUTION OF CLEARED CHANNELS IN NEUTRON-IRRADIATED PURE COPPER AS A FUNCTION OF TENSILE STRAIN—D. J. Edwards (Pacific Northwest National Laboratory)* and B. N. Singh (Risø National Laboratory, Denmark), pp. 136-138.
2. DISLOCATION DENSITY-BASED CONSTITUTIVE MODEL FOR THE MECHANICAL BEHAVIOR OF IRRADIATED CU—A. Arsenlis (Lawrence Livermore National Laboratory), B. D. Wirth (Department of Nuclear Engineering, University of California Berkeley), and M. Rhee (Lawrence Livermore National Laboratory), pp. 139.

5_REFRACTORY METALS AND ALLOYS

• No contributions

6_AUSTENITIC STAINLESS STEELS

1. THE STRONG INFLUENCE OF DISPLACEMENT RATE ON VOID SWELLING IN VARIANTS OF FE-16CR 15NI-3MO AUSTENITIC STAINLESS STEEL IRRADIATED IN BN-350 AND BOR-60—N. I. Budylkin, E. G. Mironova, N. M. Mitrofanova, and V. M. Chernov (Bochvar Institute of Non-Organic Materials), S. I. Porollo (Institute of Physics and Power Engineering), T. M. Bulanova, V. K. Shamardin (Research Institute of Atomic Reactors), and F. A. Garner (Pacific Northwest National Laboratory)*, pp. 142 146.
2. INFLUENCE OF RADIATION-INDUCED VOIDS AND BUBBLES ON PHYSICAL PROPERTIES OF AUSTENITIC STRUCTURAL ALLOYS—E. N. Shcherbakov, A. V. Kozlov, and I. A. Portnykh (FSUE Institute of Nuclear Materials), Iouri I. Balachov (SRI International), and F. A. Garner (Pacific Northwest National Laboratory)*, pp. 147-152.
3. CHARACTERIZATION OF STRUCTURAL CONDITIONS OF AISI 316 ANALOG STAINLESS STEEL IRRADIATED IN THE BN-350 REACTOR—O. P. Maksimkin, K. V. Tsai, L. G. Turubarova, and T. Doronina (Institute of Nuclear Physics, Almaty, Kazakhstan), and F. A. Garner (Pacific Northwest National Laboratory)*, pp. 153-159.

7_MHD INSULATORS, COATINGS, INSULATING CERAMICS, AND OPTICAL MATERIALS

1. RECENT PROGRESS IN THE DEVELOPMENT OF ELECTRICALLY INSULATING COATINGS FOR A LIQUID LITHIUM BLANKET—B. A. Pint, P. F. Tortorelli (Oak Ridge National Laboratory, USA), A. Jankowski, J. Hayes (Lawrence Livermore National Laboratory, USA), T. Muroga, A. Suzuki (NIFS, Japan), O. I. Yeliseyeva (G. V. Karpenko Physico-Mechanical Institute NASU, Ukraine), and V. M. Chernov (Bochvar Institute of Inorganic Materials, Russia), pp. 161-169.

8_BREEDING MATERIALS

• No Contributions

9_RADIATION EFFECTS, MECHANISTIC STUDIES, AND EXPERIMENTAL METHODS

1. THE EFFECTS OF INTERFACES ON RADIATION DAMAGE PRODUCTION IN LAYERED METAL COMPOSITES—H. L. Heinisch, F. Gao, and R. J. Kurtz (Pacific Northwest National Laboratory)*, pp. 172-178.
2. MULTISCALE MODELING OF RADIATION DAMAGE IN FE-BASED ALLOYS IN THE FUSION ENVIRONMENT—B. D. Wirth (Department of Nuclear Engineering, University of California Berkeley), G. R. Odette (University of California, Santa Barbara), J. Marian (California Institute of Technology), L. Ventelon (University of California, Berkeley), J. A. Young and L. A. Zepeda-Ruiz (Lawrence Livermore National Laboratory), pp. 179.
3. INFLUENCE OF PKA DIRECTION, FREE SURFACES, AND PRE-EXISTING DEFECTS ON CASCADE DAMAGE FORMATION—R. E. Stoller, S. G. Guiriec (Oak Ridge National Laboratory), pp. 180-189.
4. DISLOCATION INTERACTIONS WITH VOIDS AND HELIUM BUBBLES IN FCC METALS—J. A. Young (Lawrence Livermore National Laboratory), B. D. Wirth (Department of Nuclear Engineering, University of California Berkeley), J. Robach, and I. M. Robertson (University of Illinois, Urbana Champaign), pp. 190.
5. THE EFFECTS OF GRAIN BOUNDARY STRUCTURE ON BINDING OF He IN Fe—R. J Kurtz and H. L. Heinisch, Jr. (Pacific Northwest National Laboratory)*, pp. 191-194.
6. DISLOCATION-STACKING FAULT TETRAHEDRON INTERACTION: WHAT WE CAN LEARN FROM ATOMIC SCALE MODELING—Yu. N. Osetsky, R. E. Stoller, and Y. Matsukawa (Oak Ridge National Laboratory)*, pp. 195-200.
7. KINETIC MONTE CARLO SIMULATIONS OF DISLOCATION DECORATION AND RAFT FORMATION IN BCC-IRON UNDER CASCADE IRRADIATION–M. Wen, N. M. Ghoniem (Department of Mechanical and Aerospace Engineering, University of California, Los Angeles), and B. N. Singh (Risø National Laboratory, Denmark), pp. 201-208.
8. MODELING THE BRITTLE-DUCTILE TRANSITION IN FERRITIC STEELS— S. J. Noronha and N. M. Ghoniem (University of California, Los Angeles), pp. 209-212.
9. MD AND KMC MODELING OF THE GROWTH AND SHRINKAGE MECHANISMS OF HELIUMVACANCY COMPLEXES IN FE—K. Morishita, R. Sugano (Institute for Advanced Energy, Kyoto University), and B. D. Wirth (Department of Nuclear Engineering, University of California Berkeley), pp. 213.
10. NUCLEATION AND GROWTH OF HELIUM-VACANCY CLUSTERS IN IRRADIATED METALS. PART II. A GROUPING METHOD FOR AN APPROXIMATE SOLUTION OF TWO DIMENSIONAL KINETIC EQUATIONS DESCRIBING EVOLUTION OF POINT DEFECT CLUSTERS TAKING INTO ACCOUNT BROWNIAN MOTION OF THE CLUSTERS—S. I. Golubov, R. E. Stoller, S. J. Zinkle (Oak Ridge National Laboratory)*, pp. 214-231.

10_DOSIMETRY, DAMAGE PARAMETERS, AND ACTIVATION CALCULATIONS

1. IMPACT OF TRANSMUTATION ISSUES ON INTERPRETATION OF DATA OBTAINED FROM FAST REACTOR IRRADIATION EXPERIMENTS—L. R. Greenwood and F. A. Garner (Pacific Northwest National Laboratory)*, pp. 233-239.

11_MATERIALS ENGINEERING AND DESIGN REQUIREMENTS

• No Contributions

12_IRRADIATION FACILITIES AND TEST MATRICES

1. ASSEMBLY OF THE MFE-RB-17J EXPERIMENT—A. L. Qualls, K. R. Thoms, D. W. Heatherly, and R. G. Sitterson (Oak Ridge National Laboratory), pp. 242-249.
2. ASSEMBLY OF THE US-JAPAN JP-26 EXPERIMENT AND START OF IRRADIATION IN THE HFIR— K. R. Thoms, D. W. Heatherly, S. H. Kim, R. G. Sitterson, R. E. Stoller (Oak Ridge National Laboratory), and H. Tanigawa (Japan Atomic Energy Research Institute, Tokai, Japan), pp. 250-263.