DOE/ER-0313/34 - Volume 34
Semiannual Progress Report
June 30, 2003

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

1_VANADIUM ALLOYS

1. ELECTRICAL RESISTIVITY DATA OF VANADIUM ALLOYS IN THE RB-17J EXPERIMENT – M. Li, D. T. Hoelzer and S. J. Zinkle (Oak Ridge National Laboratory), pp. 2-5.
2. FABRICATION OF CREEP TUBING FROM THE US AND NIFS HEATS OF V-4Cr-4Ti - A. F. Rowcliffe, D. T. Hoelzer (Oak Ridge National Laboratory), W. R. Johnson (RSME Services, San Diego), C. Young (Century Tubes Inc, San Diego), pp. 6-21.
3. PROCESSING AND FABRICATION OF EXPERIMENTAL VANADIUM ALLOYS FOR HFIR RB-17J EXPERIMENT - D. T. Hoelzer, A. F. Rowcliffe, and L. T. Gibson (Oak Ridge National Laboratory), pp. 22-26.
4. CHARACTERIZATION OF REACTION PRODUCTS AFTER OXIDATION OF V-4Cr-4Ti AT LOW PRESSURES - B. A. Pint and H. M. Meyer (Oak Ridge National Laboratory), pp. 27-29.
5. STRONGLY NON-ARRHENIUS INTERSTITIAL DIFFUSION IN VANADIUM - L. A. Zepeda- Ruiz (Lawrence Livermore National Laboratory), S. Han (Princeton University), G. J. Ackland (University of Edinburgh), R. Car (Princeton University), and D. J. Srolovitz (Princeton University), pp. 30.
6. ON THE CHARACTER OF SELF-INTERSTITIAL LOOPS IN VANADIUM - L. A. Zepeda- Ruiz (Lawrence Livermore National Laboratory), J. Marian (Lawrence Livermore National Laboratory), B. D. Wirth (University of California Berkeley), and D. J. Srolovitz (Princeton University), pp. 31.
7. MOLECULAR DYNAMICS STUDY OF THE THRESHOLD DISPLACEMENT ENERGY IN VANADIUM - L. A. Zepeda-Ruiz (Princeton University and Lawrence Livermore National Laboratory), S. Han (Princeton University), D. J. Srolovitz (Princeton University), R. Car (Princeton University) and B. D. Wirth (University of California, Berkeley), pp. 32.

2_CERAMIC COMPOSITE MATERIALS

1. CHARACTERIZATION OF A 2D-SICF/SIC COMPOSITE MADE BY ICVI WITH HI-NICALON™ TYPE S FABRIC – G. E. Youngblood and R. H. Jones (Pacific Northwest National Laboratory), pp. 34-40.
2. THERMAL DIFFUSIVITY/CONDUCTIVITY OF IRRADIATED HI-NICALON™ 2D-SICF/SIC COMPOSITE - G. E. Youngblood, D. J. Senor and R. H. Jones (Pacific Northwest National Laboratory), pp. 41-47.
3. NOTE: This report was inadvertently left out of the previous FMSPR (DOE/ER-0313/33). Two companion papers did appear in the previous FMSPR, “Thermal diffusivity/conductivity of irradiated Sylramic™ 2D-SiCf/SiC composite” and “Thermal diffusivity/conductivity of irradiated monolithic CVDSiC.” For continuity, these reports should be read in sequence since the details for all three experiments and the description of the H2L model are given in this report.

3_FERRITIC/MARTENSITIC STEELS

1. FRACTURE TOUGHNESS VARIABILITY IN F82H - D. S. Gelles (Pacific Northwest National Laboratory) and Mikhail A. Sokolov (Oak Ridge National Laboratory), pp. 49-55.
2. FURTHER EXAMINATION OF CRACK TIP MICROSTRUCTURES IN F82H ON THE LOWER SHELF - D. S. Gelles (Pacific Northwest National Laboratory), G. R. Odette (University of California at Santa Barbara) and P. Spätig (École Polytechnique Fédérale de Lausanne, – Centre de Recherches en Physique des Plasma, Villigen PSI, Switzerland), pp. 56-62.
3. IRRADIATION EFFECTS ON IMPACT TOUGHNESS OF LOW-CHROMIUM BAINITIC STEELS – R. L. Klueh and M. A. Sokolov (Oak Ridge National Laboratory), pp. 63-69.
4. IRRADIATION CREEP AND SWELLING OF RUSSIAN FERRITIC-MARTENSITIC STEELS IRRADIATED TO VERY HIGH EXPOSURES IN THE BN-350 FAST REACTOR AT 305- 335°C – Y. V. Konobeev, A. M. Dvoriashin, S. I. Porollo, and S. V. Shulepin. (Institute of Physics and Power Engineering, Russia), N. I. Budylkin, and E. G. Mironova (Research Institute of Inorganic Materials, Russia) F. A. Garner and M. B. Toloczko (Pacific Northwest National Laboratory), pp. 70-77.

4_COPPER ALLOYS

1. STATUS OF IN-REACTOR TENSILE STRAINING OF PURE COPPER AT A CONSTANT STRAIN RATE - D. J. Edwards (Pacific Northwest National Laboratory), B. N. Singh (Risø National Laboratory, Denmark), S. Tähtinen, P. Moilanen (VTT Industrial Systems, Finland), P. Jacquet and J. Dèkeyser (Reactor Technology Department, SCK·CEN, Belgium), pp. 79-84.
2. THE EFFECT OF POST-IRRADATION ANNEALING ON STACKING FAULT TETRAHEDRA IN NEUTRON-IRRADIATED OFHC COPPER - D. J. Edwards (Pacific Northwest National Laboratory), B. N. Singh and M. Eldrup (Risø National Laboratory, Denmark), pp. 85-92.

5_REFRACTORY METALS AND ALLOYS

• No Contributions

6_AUSTENITIC STAINLESS STEELS

• No Contributions

7_MHD INSULATORS, INSULATING CERAMICS AND OPTICAL MATERIALS

1. STUDY OF THE LONG-TERM STABILITY OF MHD COATINGS FOR FUSION REACTOR APPLICATIONS - B. A. Pint and L. D. Chitwood (Oak Ridge National Laboratory, USA) and A. Suzuki (NIFS, Japan), pp. 96-98.

8_BREEDING MATERIALS

• No Contributions

9_RADIATION EFFECTS, MECHANISTIC STUDIES, AND EXPERIMENTAL METHODS

1. DEFORMATION AND FRACTURE MECHANISMS IN IRRADIATED FCC AND BCC METALS – S. J. Zinkle (Oak Ridge National Laboratory) and G. E. Lucas (University of California-Santa Barbara), pp. 101-125.
2. ATOMIC-LEVEL INTERACTION OF AN EDGE DISLOCATION WITH LOCALIZED OBSTACLES IN FCC AND BCC METALS - Yu. N. Osetsky (Oak Ridge National Laboratory) and D. J. Bacon (Department of Engineering, The University of Liverpool, UK), pp. 126-132.
3. A KINETIC MONTE CARLO MODEL FOR HELIUM DIFFUSION AND CLUSTERING IN FUSION ENVIRONMENTS - B. D. Wirth (University of California, Berkeley) and E. M. Bringa (Lawrence Livermore National Laboratory), pp. 133.
4. SUPPRESSION OF HELIUM BUBBLE GROWTH IN FRICTION STIR WELDING OF IRRADIATED MATERIALS – Zhili Feng and Stan A. David (Oak Ridge National Laboratory), pp. 134-138.

10_DOSIMETRY, DAMAGE PARAMETERS, AND ACTIVATION CALCULATIONS

• No Contributions

11_MATERIALS ENGINEERING AND DESIGN REQUIREMENTS

• No Contributions

12_IRRADIATION FACILITIES AND TEST MATRICES

• PLANNING OF THE US-JAPAN JP-26 EXPERIMENT FOR IRRADIATION IN THE HFIR - R. E. Stoller (Oak Ridge National Laboratory) and H. Tanigawa (Japan Atomic Energy Research Institute, Tokai, Japan), pp. 142-147.