The intermediate to advanced class will be held for people who have used MCNP and want to extend their knowledge and understanding of the code system.

The class will be based on MCNP5 and will cover the new capabilities of version 5. Attendees may elect to receive the new package. If you have previously received an older registered version of MCNP from RSICC, you may request that the MCNP5 package be sent to you at no charge. If you have not received an older version of MCNP from RSICC, you will be charged the applicable transmittal fee.

The other capabilities of MCNP will also be covered, including basic and advanced geometry, source definitions, tallies, data, variance reduction, statistical analysis, criticality, plotting of geometry, and particle tracks, neutron/photon/electron physics.

All classes provide interactive computer instruction. Time will be available to discuss individual questions and problems with MCNP experts or to pursue in more detail topics mentioned in the talks. Please note that other classes are offered based on MCNP. The classes mentioned here are the only ones that are taught by the people who develop and write MCNP.

MCNP Visual Editor Classes

The Visual Editor is a powerful visualization tool that can be used to rapidly create complex Monte Carlo N Particle (MCNP5) geometry models, including lattices, universes, fills, and other geometrical transformations. The Visual Editor can:

Training class is scheduled March 15-19, 2004, in Richland, Washington. The class will focus on the use of the visual editor, with an overview of MCNP. The fifth day is optional and will focus on using the Visual Editor and MCNP to do some example problems.

The class combines teaching on MCNP physics, along with instructions on how to use the Visual Editor. Computer demonstrations and exercises will focus on creating and interrogating input files with the Visual Editor. Demonstrations of advanced visualization work using MCNP will also be made. The class will be taught on Pentium computers running Windows 2000. Attendees are encouraged to bring their own input files for viewing and modifying in the visual editor. For a more detailed description of this course, click here. Further information on this class can be located at: http://www.mcnpvised.com/train.html, or by contacting Randy Schwarz (email randyschwarz@mcnpvised.com).

MCNPX Workshops

MCNPX is the LANL all-particle, all-energy (eV-TeV) Monte Carlo transport code based on MCNP4C, LAHET, CEM, etc. MCNPX has been in active development since 1995, sponsored by the particle accelerator community. It has now become an accepted tool for a broad range of applications by nuclear engineers, physicists, and scientists. The MCNPX development effort has expanded the use of the Los Alamos tools to applications such as APT, waste transmutation, accelerator shielding and health physics, particle beam cancer therapy, space shielding and cosmic ray analysis, single event effects in semiconductors, radiography, and more detailed analysis of the effects of light and heavy ions in matter. In addition, the entire functionality of MCNP4C is retained. New variance reduction and data analysis techniques, many adapted from high energy accelerator methodologies, have also been added, such as the extensive 'mesh tally' capability which allows up to 3-d plotting of particle tracks, fluence and fluence-derived quantities, energy deposition, next event estimator generation contributions and particle sources.

The workshops include hands-on instruction, generally on PC Windows machines. Subject to participant export approval for the MCNPX beta test team, participants will be able to access the Fortran-90 version of MCNPX 2.4, the LA150 (150 MeV) cross-section data for over 40 isotopes for incident neutrons and protons, and 12 for photonuclear interactions, and a notebook of viewgraphs. Follow-up consultation for class participants will be provided.

Classes are taught by experienced MCNPX code developers and instructors. More information on code versions and capabilities is available at MCNPX Workshops web site http://mcnpxworkshops .com.

PHYSOR 2004

The Chicago Section of the American Nuclear Society is pleased to announce that it will host the PHYSOR-2004 Topical Meeting, April 25-29, 2004, in Chicago, Illinois. The meeting is co-sponsored by the Reactor Physics Division of the ANS, OECD Nuclear Energy Agency, European Nuclear Society, Canadian Nuclear Society, and the Brazilian National Atomic Energy Commission. The conference will be held at the Hyatt Regency in downtown Chicago.

The title for the meeting is "The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments." The technical program will cover more than 15 topical focus areas. You are invited to visit the meeting website at www.physor2004.anl.gov to obtain updated information and to download a copy of the meeting announcement. Contact: Ray Klann, Technical Program Co-Chair, at 630-252-4305 or klann@anl.gov.

Practical MCNP for the HP, Medical Physicist, and Rad Engineer

Monte Carlo type calculations are ideally suited to solving a variety of problems in radiation protection and dosimetry. This course is aimed at the health physicist, medical physicist, and rad engineer with no prior experience with Monte Carlo techniques. The focus is almost entirely on the application of MCNP™ to solve a variety of practical problems in radiation shielding and dosimetry. The intent is to "jump start" the student toward using MCNP productively. Extensive interactive practice sessions are conducted on a personal computer. Topics will include an overview of the MCNP code and the Monte Carlo method, input file preparation, geometry, source definition, standard MCNP tallies, interpretation of the output file, exposure and dose rate calculations, radiation shielding, photon skyshine, detector simulation and dosimetry. Students will be provided with a comprehensive class manual and a diskette containing all of the practice problems. This course has been granted 32 Continuing Education Credits by the AAHP, and 4.5 CM points by the American Board of Industrial Hygiene. The course is offered by the Health Physics Measurements Group at the Los Alamos National Laboratory and is co-sponsored by RSICC.

Registration is available online at: http://drambuie.lanl.gov/~esh4/mcnp.htm. Make checks payable to the University of California (checks must be in U.S. dollars on a U.S. bank) and mail together with name, address, and phone number to: Los Alamos National Laboratory, Group HSR-4, MCNP Class, David Seagraves, Mail Stop J573, Los Alamos, NM 87545.

Inquiries regarding registration and class space availability should be made to David Seagraves, 505-667-4959, fax: 505-665-7686, e-mail: dseagraves@lanl.gov. Technical questions may also be directed to Dick Olsher, 505-667-3364; e-mail: dick@lanl.gov.

Please note that this course is separate from and independent of the courses being offered by the MCNP and MCNPX Teams at LANL.

SCALE TRAINING COURSES

The SCALE staff at Oak Ridge National Laboratory (ORNL) will be offering three training courses this spring, April 26-30, May 3-4, and May 5-7, 2004. The courses will emphasize hands-on experience solving practical problems on PCs. There will be workgroups of two persons each. Courses are open to both new and experienced SCALE users. Registration must be submitted by March 26, 2004. After that date a surcharge of $300 will be added to the fee.

Classes are cosponsored by RSICC which offers a discounted price of $200 (single user license) to all attendees for the SCALE software and manual on CD.

Registration forms should be submitted from the Web. Registration via fax is also acceptable. The registration fee may be paid by check, bank transfer, or credit card (VISA or MasterCard only). Course agendas and description information are found at http://www.ornl.gov/sci/scale/trcourse.html. Class size is limited and courses are subject to cancellation if minimum enrollment is not obtained one month prior to the course. Course fees are refundable up to one month before each class.

Foreign nationals must register at least eight weeks in advance to obtain security clearance. For further information, contact Kay Lichtenwalter, scalecoding@ornl.gov, 865-574-9213.

Short Course on "Introduction to Monte Carlo Treatment Planning"

The course registration fee is $1600, which covers the course materials, two lunches, two dinners and refreshments. A set of software is free for the attendee. Discounts for students are available. Hotel information is available upon request.

The short course is designed to train future Monte Carlo RTP users and researchers in the use of Monte Carlo treatment planning software. The course will include didactic instruction and hands-on workshops. The course is specially suited for previous EGS4 and OMEGA/BEAM course participants, who want to expand their research into clinical RTP. A working knowledge of a Unix-based system is expected to run the Monte Carlo RTP software.

Enrollment will be limited to 20 people to facilitate instruction at the hands-on labs. So please register early. Registration will be strictly on a first-come basis. Please contact Dr. Jinsheng Li, at js_li@fccc.edu or see the website: http://www.fccc.edu/clinical/radiation_oncology/ monte_carlo_course.html.

2005 Conferences

Monte Carlo 2005 Topical Meeting

Monte Carlo 2005 will be held April 17-21, 2005, (Sunday-Thursday). The theme of the conference will be "The Monte Carlo Method: Versatility Unbounded in A Dynamic Computing World".

The conference site is the Chattanooga Marriott and Convention Center in Chattanooga, Tennessee. The conference will be hosted by the American Nuclear Society (ANS) Oak Ridge/Knoxville Section, with ANS Radiation Protection and Shielding Division (RPSD) as the sponsoring division and Mathematics and Computations Division (MCD) as a co-sponsor. Co-sponsors will also include Oak Ridge National Laboratory (ORNL), Radiation Safety Information Computational Center (RSICC) and the Organization for Economic Cooperation and Development (OECD) Nuclear Energy Agency Data Bank (NEADB).

The Monte Carlo method and its applications have been frequently addressed at several major conferences and workshops organized in recent years in the area of nuclear applications. Monte Carlo topics have included radiation shielding, radiation physics, medical physics, and high energy physics. Significant developments have taken place in computational and data issues, resulting in state-of-the-art computer codes and tools. Monte Carlo 2005 is the next in a series devoted to the topic, following Monte Carlo 2000 which was held in Lisbon, Portugal, in October 2000.

Conference topics will include: Methods Advancements (Physics) (proton transport, neutron transport, gamma transport, electron transport, heavy ion transport); Nuclear Data Advancements (proton transport, neutron transport, gamma transport, electron transport, heavy ion transport); Mathematical and Computational Advances (experiments & benchmarks, mathematical advances, computational advances, visualization); Applications (reactor, medical, accelerator, neutron science, dosimetry, shielding, fuel cycle, waste management, space & aviation, fusion, criticality safety, non-nuclear applications).

The website is http://MonteCarlo2005.org. Full papers are due September 10, 2004. For information contact Bernadette Kirk (kirkbl@ornl.gov, 865-574-6176), General Chair, or Jeff Johnson (johnsonjo@ornl.gov, 865-574-5262), Technical Chair.

Twelfth International Symposium on Reactor Dosimetry

The Twelfth International Symposium on Reactor Dosimetry will be held May 8-13, 2005, in Gatlinburg, Tennessee.

This Symposium is held approximately every three years to provide a forum for the interchange of state-of-the-art techniques, data bases and standardization of radiation metrology. The Symposium will be of value to those involved in reactor dosimetry, including researchers, manufacturers and representatives from industry, utilities and regulatory agencies.

This Symposium is jointly sponsored by ASTM International, the European Working Group on Reactor Dosimetry (EWGRD), and the Atomic Energy Society of Japan (AESJ). It is organized by ASTM Committee E10 on Nuclear Technology and Applications and EWGRD.

The Symposium will be organized into oral and poster presentations, informal round-table workshops and tutorials. The meeting language will be English. No translations will be provided.

All papers presented at the Symposium will be subject to peer-review before acceptance for publication in the on-line Journal of ASTM International. Registrants will receive a complimentary CD of the papers presented at the Symposium. For more information visit the website at: http://reactordosimetry.com/.

CALENDAR

April 2004

PHYSOR 2004 Reactor Physics Topical Meeting, Apr. 25-29, 2004, Chicago, IL. Jointly sponsored by the Reactor Physics Division of the ANS and the Nuclear Energy Agency of the OECD and others. Contact: Ray Klann (tel 630-252-4305, email klann@anl.gov, url http://www.physor2004.anl.gov/).

9th Workshop on Monte Carlo Simulation of Radiotherapy Treatment Sources Using the BEAM Code System, Apr. 26-29, 2004, Ottawa, Canada. Contact: Dave Rogers (tel 613-520-2600 x4374, fax 613-520-4061, email drogers@physics.carleton.ca, url www.physics.carleton.ca/~drogers/BEAM/course/brochure.html).

May 2004

Current Topics in Monte Carlo Treatment Planning, May 3-5, 2004, McGill University, Montreal, Canada. Contacts: Jan Seutjens and Frank Verhaegen (tel 514-934-8052, url http://mctp.medphys.mcgill.ca).

MCNPX Intermediate Workshop, May 3-7, 2004, Lisbon, Portugal Contact: Bill Hamilton (tel 505-455-0312, email registrar@mcnpxworkshops.com, url http://mcnpxworkshops.com for details).

International Conference on Radiation Shielding (ICRS-10) and Topical Mtg. on Radiation Protection & Shielding (RPS 2004), May 9-14, 2004, Funchal, Madeira Island (Portugal). Contact: Conference Secretariat (email icrs-rps@itn.mces.pt, url http://www.itn.mces.pt/ICRS-RPS).

5th Intl. Conference on Nuclear Option in Countries with Small and Medium Electricity Grids, May 16-20, 2004., Dubrovnik, Croatia, Contact Prof. Nenad Debrecin (tel +385- 1-6312-399, email hnd2004@fer.hr, url http://hnd.zvne.fer.hr/Dubrovnik2004).

June 2004

Practical MCNP for the HP, Medical Physicist, and Rad Engineer, June 7-11, 2004, Univ. of New Mexico, Los Alamos Campus. Contact: David Seagraves, (tel 505-667-4959, fax 505-665-7686, e-mail dseagraves@lanl.gov. Technical questions may also be directed to Dick Olsher, 505-667-3364; e-mail dick@lanl.gov, url http://drambuie.lanl.gov/~esh4/mcnp.htm).

MCNPX Introductory Workshop, June 7-11, 2004, Santa Fe, NM. Contact: Bill Hamilton (tel 505-455-0312, email registrar@mcnpxworkshops.com, url http://mcnpxworkshops.com for details).

July 2004

MCNPX Intermediate Workshop, July (TBA), 2004, Houston, TX. Contact: Bill Hamilton (tel 505-455-0312, email registrar@mcnpxworkshops.com, url http://mcnpxworkshops.com for details).

September 2004

1st International Symposium on Radionuclide Therapy and Radiopharmaceutical Dosimetry, Sept. 4-8, 2004, Helsinki, Finland. Contact: Michael Lassmann or Val Lewington, (emails lassmann@ nuklearmedizin.uni-wuerzburg.de; vjlewington@ hotmail.com).

16th American Nuclear Society Topical Meeting on the Technology of Fusion Energy, Sept. 14-16, 2004, Madison, WI. (url http://fti.neep.wisc.edu/tofe).

International Conference on Nuclear Data for Science and Technology "ND2004", Sept. 26-Oct. 1, 2004, Santa Fe, NM. (Contact: http://t16web.lanl.gov/nd2004/).

5th International Conference of Yugoslav Nuclear Society (YUNS) - 2004, Sept. 27-30, 2004, Belgrade, Serbia & Montenegro. Contact: Dr. Milan Pesic, (tel 381-11-245-82-22/ext. 681, email mpesic@vin.bg.ac.yu, url http://www.vin.bg.ac.yu/YUNS/index.htm).

October 2004

11th World Congress on Neutron Capture Therapy (ISNCT-11), Oct. 11-15, 2004, Boston, MA. Contact: Robert G. Zamenhof (tel 617-636-1681, fax 617-636-5867, email rzamenhof@tufts-nemc.org, url http://meetingsandconferences.com/ISNCT-11/).

April 2005

Monte Carlo 2005 Topical Meeting, Apr. 17-21, 2005, Chattanooga, TN. Contact: Bernadette Kirk (tel 865-574-6176, fax 865-241-4046, email kirkbl@ornl.gov, url http://meetingsandconference.com /MonteCarlo2005).

ACCESSION OF NUCLEAR SYSTEMS LITERATURE

The nuclear systems literature (shielding, safety, materials) cited below has been reviewed and placed in the RSICC Information Storage and Retrieval Information System (SARIS), now searchable on the RSICC web server (http://www-rsicc.ornl.gov/SARIS.html). We now include medical physics in addition to material science, radiation dosimetry, radiation safety, reactor dynamics, reactor safeguards, risk assessment, waste management, fuel cycle, fusion and plasmas, high energy particle transport, and shielding. This early announcement is made as a service to the nuclear sciences community. Copies of the literature are not distributed by RSICC. They may generally be obtained from the author or from a documentation center such as the National Technical Information Service (NTIS), Department of Commerce, Springfield, Virginia 22161.

Ann. Nucl. Energy, 31, 459-480. . . Minimizing the Gamma Radiation Effects to Spent Fuel Pool Walls. . . .Tippayakul, C. et al. . . . March 2004. . . Penn. State University, PA; Exelon, Corp., USA.

Ann. Nucl. Energy, 31, 481-516. . . Probabilistic Safety Analysis of a Greek Research Reactor. . . .Aneziris, O.N. et al. . . . March 2004. . . National Center for Scientific Research DEMOKRITOS, Aghia Paraskevi, Greece.

Ann. Nucl. Energy, 31, 517-540. . . Development, Assessment and Application of TRAC-BF1/v2001.2 for Beyond Design Basis BWR LOCA Transients. . . .Analytis, G.Th. et al. . . . March 2004. . . Paul Scherrer Institute, Villigen, Switzerland.

Ann. Nucl. Energy, 31, 541-576. . . Minimum Critical Mass and Flat Flux in a 2-Group Model. . . .Lewins, J. . . . March 2004. . . University of Cambridge, United Kingdom.

Ann. Nucl. Energy, 31, 577-582. . . The Photon Attenuation Coefficients of Barite, Marble and Limra. . . .Akkurt, I. et al. . . . March 2004. . . Suleyman Demirel University, Isparta, Turkey.

Ann. Nucl. Energy, 31, 583. . . Book Review: Understanding Radioactive Waste, R. L. Murray; 5th Edition, Paperback, 231 Pages, Battelle Press, Columbus, OH, 2003, ISBN 1-57477-135-3. . . .Putte, D.V. . . . March 2004. . . Electrowatt-Ekono, West Sussex, United Kingdom.

Ann. Nucl. Energy, 31, 713-722. . . Comparison Between HELIOS Critical-Depletion Calculations and a PWR Thorium Cell Burnup Benchmark. . . .Nunez-Carrera, A. et al. . . . May 2004. . . Comision Nacional de Seguridad Nuclear y Salvaguardias, Navarte, Mexico; Universidad Nacional Autonoma de Mexico, Mor., Mexico; Universidad Metropolitana, Vicentia, Mexico.

Ann. Nucl. Energy, 31, 723-736. . . Analysis of a PWR Core Baffle Considering Irradiation Induced Creep. . . .Altstadt, E. et al. . . . May 2004. . . Institute of Safety Research, Dresden, Germany; E.ON Nuclear Power, Hannover, Germany.

Ann. Nucl. Energy, 31, 737-745. . . Cold and Thermal Neutron Scattering Cross Sections of Liquid H2 and D2. II: Improvement on Coherent Scattering. . . .Morishima, N. et al. . . . May 2004. . . Kyoto University, Japan.

Ann. Nucl. Energy, 31, 747-772. . . Development of the VVER Core Loading Optimization System. . . .Guler, C. et al. . . . May 2004. . . Penn. State University, University Park, PA; SKODA, Plzen, CzechRepublic.

Ann. Nucl. Energy, 31, 773-788. . . On-Line Channel Instability Localisation with Fuzzy Rule-Based Systems. . . .Tambouratzis, T. et al. . . . May 2004. . . Institute of Nuclear Technology, Athens, Greece; Aristotle University of Thessaloniki, Greece.

Ann. Nucl. Energy, 31, 789-803. . . Using a Multi-State Recurrent Neural Network to Optimize Loading Patterns in BWRs. . . .Ortiz, J.J. et al. . . . May 2004. . . ININ, Mexico; University Granada, Spain.

Ann. Nucl. Energy, 31, 805-811. . . Radiation Effects on the Resolution (MTF) of the Scintillator Coupled CMOS APS Array Imager for Non-Destructive Test X-Ray Imaging. . . .Kim, K.H. et al. . . . May 2004. . . KAIST, Daejeon, South Korea.

Ann. Nucl. Energy, 31, 813-821. . . ADS Subcriticality Evaluation Based on the Generalized Reactivity Concept. . . .Gandini, A. . . . May 2004. . . University of Rome, Italy.

Ann. Nucl. Energy, 31, 823. . . Addendum to "On the Collision Probability for the Infinite Cylinder". . . .Corngold, N. . . . May 2004. . . California Institute of Technology, Pasadena, CA.

Ann. Nucl. Energy, 31, 825-847. . . Cell Homogenization Methods for Pin-By-Pin Core Calculations Tested in Slab Geometry. . . .Yamamoto, A., et al. . . . May 2004. . . Nagoya University, Japan.

Ann. Nucl. Energy, 31, 849-869 . . Development of Automated Operating Procedure System Using Fuzzy Colored Petri Nets for Nuclear Power Plants. . . .Lee, S.J. et al. . . . May 2004. . . Korea Advanced Institute of Science and Technology, Daejeon, South Korea.

Ann. Nucl. Energy, 31, 871-890. . . LWR Spent Fuel Transmutation in a High Power Density Fusion Reactor. . . .Sahin, S. et al. . . . May 2004. . . Gazi Universitesi, Ankara, Turkey.

Ann. Nucl. Energy, 31, 891-909. . . Computing Neutron Detector Response to Power Reactor Mechanical Structure Vibrations. . . .Dobrea, D. et al. . . . May 2004. . . Institute for Nuclear Research, Pitesti, Romania.

Ann. Nucl. Energy, 31, 911-921. . . Thermal Neutron Cross-Sections of Magnesium. . . .Mounier, C. . . . May 2004. . . CEA-Saclay, Gif-sur-Yvette, France.

Ann. Nucl. Energy, 31, 923-931. . . View-CXS Neutron and Photon Cross-Sections Viewer.. . .Subbaiah, K.V. et al. . . . May 2004. . . Safety Research Institute, Tamilnadu, India.

Ann. Nucl. Energy, 31, 933-946. . . The Extinction Problem in a Super-Critical Sphere of Fissile Material. . . .Williams, M.M.R. . . . May 2004. . . Imperial College of Science, Technology, and Engineering, London, United Kingdom.

Ann. Nucl. Energy, 31, 947-960. . . Modeling of the Interfacial Shear in the 3D Momentum Equations of TRAC-BF1. . . .Analytis, G. Th. . . . May 2004. . . Paul Scherrer Institute, Villigen, Switzerland.

Fusion Eng. Design, 70, 1-3. . . International Science and Technology Center, A Decade of Joint Efforts for a Safer World. . . .Kroening, M. . . . January 2004. . . International Science & Technology Center, Moscow, Russia.

Fusion Eng. Design, 70, 5-11. . . Efficiency Measurement of 6LiD Converter of Thermal to Fast Neutrons of (DT), (6LiD) Fusion with 14 MeV Energy in IVV-2M Reactor Experimental Channel. . . .Zouev, Yu. N. et al. . . . January 2004. . . Russian Federal Nuclear Center, Snezhinsk, Russia; Sverdlovsk Branck of NIKIET, Russia.

Fusion Eng. Design, 70, 13-33. . . Gas Dynamic Trap as High Power 14 MeV Neutron Source. . . .Bagryansky, P.A. et al. . . . January 2004. . . Budker Institute of Nuclear Physics, Novosibirsk, Russia; Institute of Technical Physics, Snezhinsk, Russia.

Fusion Eng. Design, 70, 35-43. . . Fusion in the Magnetically Compressed Targets. . ..Mokhov, V.N. et al. . . . January 2004. . . Russian Federal Nuclear Center, Sarov, Russia.

Fusion Eng. Design, 70, 45-56. . . The Development of Low Aspect Ratio Tokamaks in Russia. . . .Azizov, E.A. et al. . . . January 2004. . . RF State Scientific Center, TRINITI, Troitsk, Russia; RSC Kurchatov Institute, Moscow, Russia; Efermov Institute of Electrophysical Apparatus, St. Petersburg, Russia.

Fusion Eng. Design, 70, 57-66 . . The Effect of Tritium and Neutron Irradiation on the Structure and Properties of Reactor Steels and Alloys. . . .Sagaradze, V.V. et al. . . . January 2004. . . Institute of Metal Physics, Ekaterinburg, Russia; Russian Federal Nuclear Center, Snezhinsk, Russia.

Fusion Eng. Design, 70, 67-77. . . Tritium Permeation Through Martensitic Steel from Li17Pb83 in In-Pile Reactor Experiments. . . .Shestakov, V. . . . January 2004. . . Scientifically Research Institute of Experimental and Theoretical Physics, Almaty, Kazakhstan.

Fusion Eng. Design, 70, 79-85. . . Creep Surge Effect Under Cyclic Irradiation of Structural Materials for Fusion Reactors.. . .Tsepelev, A.B. . . . February 2004. . . Russian Academy of Sciences, Moscow, Russia.

Fusion Eng. Design, 70, 87-93. . . Fabrication of CaO Insulator Coatings by MOCVD for Application in Vanadium/Lithium Blankets. . . .Zeng, Z. et al. . . . February 2004. . . Argonne National Laboratory, Argonne, IL.

Fusion Eng. Design, 70, 115-122. . . Trends in Computing Systems for Large Fusion Experiments. . . .How, J.A. et al. . . . February 2004. . . Euratom-CEA, St. Paul lez Durance, France; Euratom-UKAEA, Abingdon, UK; Euratom-ENEA, Padova, Italy.

Fusion Eng. Design, 70, 123-129. . . Radiochemical Reactions Between Tritium Oxides and Carbon Monoxide. . . .Shu, W.M. et al. . . . February 2004. . . JAERI, Ibaraki, Japan.

Fusion Eng. Design, 70, 141-153. . . Positron Annihilation Investigations of Defects in Copper Alloys Selected for Nuclear Fusion Technology. . . .Slugen, V. et al. . . . February 2004. . . Slovak University of Technology, Bratislava, Slovak Republic; Charles University, Prague, Czech Republic; Universitat der Bundeswehr Munchen, Neubiberg, Germany.

Fusion Eng. Design, 70, 155-162 . . Monte Carlo Based Operational and Shutdown Dose Rate Calculations of HT-7U Tokamak. . . .Chen, Y. et al. . . . February 2004. . . Institut fur Reaktorsicherheit, Karlsruhe, Germany; Institute of Plasma Physics of Chinese Academy of Sciences, Anhui, China.

Fusion Eng. Design, 70, 163-173. . . Application of Glow Discharges for Tritium Removal from JT-60U Vacuum Vessel. . . .Nakamura, H. et al. . . . February 2004. . . JAERI, Ibaraki, Japan; Kyoto University, Japan; Nagoya University, Nagoya, Japan.

Fusion Eng. Design, 70, 175-183 . . Development of Plasma Stored Energy Feedback Control and Its Application to High Performance Discharges on JT-60U. . . .Oikawa, T. et al. . . . February 2004. . . JAERI, Ibaraki, Japan; Osaka University, Osaka, Japan.

J. Nucl. Mater., 324, 1-5. . . Production of Uranium-Molybdenum Particles by Spark-Erosion. . . .Cabanillas, E.D. et al. . . . January 2004. . . Consejo Nacional de Investigaciones Cientificas y Tecnicas, Buenos Aires, Argentina; Comision Nacional de Energia Atomica, Buenos Aires, Argentina; Universidad de Buenos Aires, Argentina.

J. Nucl. Mater., 324, 6-22. . . Structure of Zirconium Alloy Oxides Formed in Pure Water Studied with Synchrotron Radiation and Optical Microscopy: Relation to Corrosion Rate. . . .Yilmazbayhan, A. et al. . . . January 2004. . . Penn. State University, University Park, PA; Westinghouse Electric Co., Pittsburgh, PA; Argonne National Laboratory, IL.

J. Nucl. Mater., 324, 23-32. . . Effect of the Irradiation-Annealing-Irradiation Cycle on the Mechnaical Properties of Pure Copper and Copper Alloy. . . .Fabritsiev, S.A. et al. . . . January 2004. . . D.V. Efremov Scientific Research Institute of Electrophysical Apparatus, St. Petersburg, Russia; Scientific Research Institute of Atomic Reactors, Dimitrovgrad, Russia.

J. Nucl. Mater., 324, 33-40. . . Effect of Microstruture on the Cleavage Fracture Strength of Low Carbon Mn-Ni-Mo Bainitic Steels. . . .Im, Y-R., et al. . . . January 2004. . . Seoul National University, South Korea; Pohang Univeristy of Science and Technology, Pohang, South Korea; Hanbat National University, Taejon, South Korea; KAERI, Taejon, South Korea.

J. Nucl. Mater., 324, 41-51. . . Simulations of Low Energy Cascades in FCC Pu Metal at 300 K and Constant Volume. . . .Valone, S.M. et al. . . . January 2004. . . Los Alamos National Laboratory, Los Alamos, NM.

J. Nucl. Mater., 324, 52-61. . . Development of a Fundamental Crack Tip Strain Rate Equation and Its Application to Quantitative Prediction of Stress Corrosion Cracking of Stainless Steels in High Temperature Oxygenated Water. . . .Peng, Q.J. et al. . . . January 2004. . . Tohoku University, Sendai City, Japan.

J. Nucl. Mater., 324, 62-70. . . Microstructural Development and Radiation Hardening of Neutron Irradiated Mo-Re Alloys.. . .Nemoto, Y. et al. . . . January 2004. . . JAERI, Ibaraki-ken, Japan; Tohhoku University, Sendai City, Japan; Okayama University of Science, Okayama, Japan.

J. Nucl. Mater., 324, 71-75. . . Studies on the Corrosion Behavior of Cerium-Implanted Zirconium. . . .Peng, D.Q. et al. . . . January 2004. . . Tsinghua University, Beijing, China.

J. Nucl. Mater., 324, 77-89. . . The Change in Tensile Properties of Wrought LCAC Molybdenum Irradiated with Neutrons. . . .Cockeram, B.V. et al. . . . January 2004. . . Bettis Atomic Power Laboratory, West Mifflin, PA; Oak Ridge National Laboratory, Oak Ridge, TN.

J. Nucl. Mater., 324, 90-96. . . Modelling of Copper Precipitation in Iron During Thermal Aging and Irradiation. . . .Christien, F. et al. . . . January 2004. . . Ecole Polytechnique, Palaiseau, France.

J. Nucl. Mater., 324, 97-115. . . Modelling the Alteration Gel Composition of Simplified Borosilicate Glasses by Precipitation of an Ideal Solid Solution in Equilibrium with the Leachate. . . .Munier, I. et al. . . . January 2004. . . Ecole et Obnservatoire des Sciences de la Terre, Strasbourg, France; Ecole des Mines, Nantes, France.

J. Nucl. Mater., 324, 116-124. . . Failure Predictions for Nuclear Graphite Using a Continuum Damage Mechanics Model. . . .Zou, Z. et al. . . . January 2004. . . University of Manchester, United Kingdom.

J. Nucl. Mater., 324, 125-133. . . Mechanical Properties of Delta-Stabilized Pu-1.0 wt% Ga Alloys. . . .Robbins, J.L. . . . January 2004. . . Lawrence Livermore National Laboratory, Livermore, CA.

J. Nucl. Mater., 324, 134-139. . . Etching of Uranium Oxide with a Non-Thermal, Atmospheric Pressure Plasma. . . .Yang, X. et al. . . . January 2004. . . University of California, Los Angeles, CA; Surfx Technologies, Los Angeles, CA.

J. Nucl. Mater., 324, 140-151. . . Dynamic Strain Aging and Grain Size Reduction Effects on the Fatigue Resistance of SA533B3 Steels. . . .Huang, J.Y. et al. . . . January 2004. . . National Central University, Chung-Li, Taiwan; Institute of Nuclear Energy Research, Lungtan, Taiwan; Taiwan Power Company, Taipei, Taiwan.

J. Nucl. Mater., 324, 152-164. . . Role of Neoformed Phases on the Mechanisms Controlling the Resumption of SON68 Glass Alteration in Alkaline Media. . . .Ribet, S. et al. . . . January 2004. . . Commissariat a l'Energie Atomique, Bagnols-sur-Ceze, France.

J. Nucl. Mater., 324, 165-176. . . Comments on the Stability of Zirconium Hydride Phases in Zircaloy. . . .Lanzani, L. et al. . . . January 2004. . . CNEA, Buenos Aires, Argentina.

J. Nucl. Mater., 324, 177-182. . . Oxidation Behaviour of Uranium in the Internally Gelated Urania-Ceria Solid Solutions - XRD and XPS Studies. . . .Kumar, K.S. et al. . . . January 2004. . . Bhabha Atomic Research Centre, Tamil Nadu, India; Indira Gandhi Centre for Atomic Research, Tamil Nadu, India; IAEA, Vienna, Austria.

J. Nucl. Mater., 324, 183-188. . . Safe Trapping of Cs in Heat-Treated Zeolite Matrices. . . .Bosch, P. et al. . . . January 2004. . . Universita di Napoli Federico II, Napoli, Italy.

J. Nucl. Mater., 324, 189-197. . . Bulk and Young's Modulus of Doped UO2 by Synchrotron Diffraction Under High Pressure and Knoop Indentation. . . .Pujol, M.C. et al. . . . January 2004. . . Joint Research Centre, Karlsruhe, Germany; Charles University, Prague, Czech Republic.

J. Nucl. Mater., 324, 198-202. . . Post-Irradiation Studies on LWR-MOX Fuel Fabricated by the Optimized Co-Milling Process.. . .Kleykamp, H. . . . January 2004. . . Forschungszentrum Karlsruhe, Germany.

J. Nucl. Mater., 324, 203-214. . . Cathodoluminescence Imaging of Oxidised Zirconium Alloys. . . .Yueh, H.K. et al. . . . January 2004. . . University of Toronto, Ontario, Canada.

J. Nucl. Mater., 324, 215-219. . . Calorimetric Measurements on Uranium-Plutonium Mixed Oxides. . . .Kandan, R. et al. . . . January 2004. . . Indira Gandhi Centre for Atomic Research, Tamil Nadu, India.

J. Nucl. Mater., 325, 1-12. . . Helium Diffusion in Uranium and Plutonium Oxides.. . .Ronchi, C. et al. . . . February 2004. . . Joint Research Center, Karlsruhe, Germany.

J. Nucl. Mater., 325, 13-17. . . Corrosion Behavior of Fe-Ni-Cr Alloys in the Molten Salt of LiCl-Li2O at High Temperature. . . .Cho, S.H. et al. . . . February 2004. . . KAERI, Taejon, South Korea; Dalian University of Technology, China.

J. Nucl. Mater., 325, 18-25. . . Thermal Expansion Studies on Inconel-600 by High Temperature X-Ray Diffraction. . . .Raju, S. et al. . . . February 2004. . . Indira Gandhi Centre for Atomic Research, Kalpakkam, India.

J. Nucl. Mater., 325, 26-33 . . Stress-Reorientation of Hydrides and Hydride Embrittlement of Zr-2.5 wt% Nb Pressure Tube Alloy. . . .Singh, R.N. et al. . . . February 2004. . . Bhabha Atomic Research Centre, Mumbai, India; Indian Institute of Technology, Mumbai, India.

J. Nucl. Mater., 325, 34-43. . . Electrochemical Behaviors of Uranium and Plutonium at Simultaneous Recoveries into Liquid Cadmium Cathodes. . . .Uozumi, K. et al. . . . February 2004. . . Central Research Institute of Electric Power Industry, Tokyo, Japan; JAERI, Ibaraki-ken, Japan.

J. Nucl. Mater., 325, 44-52. . . Master Equation and Fokker-Planck Methods for Void Nucleation and Growth in Irradiation Swelling. . . .Surh, M.P. et al. . . . February 2004. . . Lawrence Livermore National Laboratory, Livermore, CA.

J. Nucl. Mater., 325, 53-60 . . Recrystallization and Precipitation Behavior of Low-Activation V-Cr-Ti Alloys After Cold Rolling. . . .Heo, N.J. et al. . . . February 2004. . . Graduate University for Advanced Studies, Gifu, Japan; National Institute for Fusion Science, Gifu, Japan.

J. Nucl. Mater., 325, 61-77. . . The Development of Grain-Face Porosity in Irradiated Oxide Fuel. . . .White, R.J. . . . February 2004. . . RW Consulting, Gloucestershire, United Kingdom.

J. Nucl. Mater., 325, 79-86. . . Hydrogen Embrittlement of a V4Cr4Ti Alloy Evaluated by Different Test Methods. . . .Chen, J. et al. . . . February 2004. . . Southwestern Institute of Physics, Chengdu, PR China; National Key Laboratory of Nuclear Fuel and Materials, Chengdu, PR China; National Institute for Fusion Science, Gifu, Japan.

J. Nucl. Mater., 325, 87-93 . . Chemical Form of Tritium Released from Solid Breeder Materials. . . .Nishikawa, M. et al. . . . February 2004. . . Kyushu University, Fukuoka, Japan.

J. Nucl. Mater., 325, 94-106. . . The Effect of Oversized Solute Additions on the Microstructure of 316SS Irradiated with 5MeV Ni++ Ions of 3.2 MeV Protons. . . .Gan, J. et al. . . . February 2004. . . Argonne National Laboratory - West, Idaho Falls, ID; Pacific Northwest National Laboratory, Richland, WA; University of Michigan, Ann Arbor, MI.

J. Nucl. Mater., 325, 107-117. . . A Model for Fission-Gas-Bubble Behavior in Amorphous Uranium Silicide Compounds. . . .Rest, J. . . . February 2004. . . Argonne National Laboratory, Argonne, IL.

J. Nucl. Mater., 325, 118-128. . . Irradiation Behaviour of Uranium Silicide Compounds. . . .Finlay, M.R. et al. . . . February 2004. . . Australian Nuclear Science and Technology Organisation, Menai, Australia; Argonne National Laboratory, Argonne, IL.

J. Nucl. Mater., 325, 129-133 . . Measurement of Gd Content in (U,Gd)O2 Using Thermal Gravimetric Analysis. . . .Kim, K.S. et al. . . . February 2004. . . KAERI, Daejon, South Korea; Chungnam National University, Daejon, South Korea.

J. Nucl. Mater., 325, 134-140. . . Novel Approach for the Bulk Synthesis of Nanocrystalline Yttria Doped Thoria Powders Via Polymeric Precursor Routes. . . .Ganesan, R. et al. . . . February 2004. . . Indira Gandhi Centre for Atomic Research, Kalpakkam, India; Pondicherry University, India; Indian Institute of Technology, Mumbai, India.

J. Nucl. Mater., 325, 141-147. . . Effect of Titania Addition on Hot Hardness of UO2.. . .Sengupta, A.K. et al. . . . February 2004. . . Bhabha Atomic Research Centre, Mumbai, India.

J. Nucl. Mater., 325, 148-158. . . Helium Thermal Diffusion in a Uranium Dioxide Matrix. . . .Roudil, D. et al. . . . February 2004. . . CEA VALRHO Maracoule, Bagnols-sur-Ceze, France; CEA SACLAY, Gif-sur-Yvette, France.

J. Nucl. Mater., 325, 159-168. . . Fabrication of (Th,U)O2 Pellets Cotaining 3Mol% of Uranium by Gel Pelletisation Technique. . . .Pai, R.V. et al. . . . February 2004. . . Bhabha Atomic Research Centre, Mumbai, India.

J. Nucl. Mater., 325, 169-173. . . Electron Spin Resonance Measurement of Irradiation Defects in Vitreous Silica Irradiated with Neutrons. . . .Moritani, K. et al. . . . February 2004. . . Kyoto University, Kyoto, Japan.

J. Nucl. Mater., 325, 174-179 . . The Second Order Raman Spectroscopy in Carbon Crystallinity. . . .Lee, Y-J. . . . February 2004. . . National Institute of Advanced Industrial Science and Technology, Ibaraki, Japan.

J. Nucl. Mater., 325, 180-187. . . Diffusion Reaction Between Zircaloy-2 and Thoria.. . .Sengupta, P. et al. . . . February 2004. . . Bhabha Atomic Research Centre, Mumbai, India.

J. Nucl. Mater., 325, 188-194. . . A General Equation of State for Dense Liquid Alkali Metals. . . .Eslami, H. . . . February 2004. . . Persian Gulf University, Boushehr, Iran.

J. Nucl. Mater., 325, 195-201 . . Immobilization of Interstitial Loops by Substitutional Alloy and Transmutation Atoms in Irradiated Metals. . . .Cottrell, G.A. et al. . . . February 2004. . . Culham Science Centre, Oxon, United Kingdom.

J. Nucl. Mater., 325, 202-209 . . Chemical Diffusion in Uranium Dioxide - Influence of Defect Interactions. . . .Ruello, P. et al. . . . February 2004. . . Ecole Centrale Paris, Chatenay Malabry, France; Commissariat a l'Energie Atomique, St.-Paul-lez-Durance, France.

J. Nucl. Mater., 325, 210-216. . . Microwave Process for Sintering of Uranium Dioxide. . . .Yang, J.H. et al. . . . February 2004. . . KAERI, Daejeon-si, South Korea.

J. Nucl. Mater., 325, 217-222 . . Excellent Corrosion Resistance of 18Cr-20Ni-5Si Steel in Liquid Pb-Bi. . . .Kurata, Y. et al. . . . February 2004. . . JAERI, Ibaraki-ken, Japan.

Nucl. Eng. Design, 227, 133-142. . . Probability Assessment of Graphite Brick in the HTR-10. . . .Yu, S. et al. . . . January 2004. . . Tsinghua University, Beijing, China.

Nucl. Eng. Design, 227, 143-153. . . Biaxial Behavior of Plain Concrete of Nuclear Containment Building. . . .Lee, S-K. et al. . . . January 2004. . . B&T Engineering Co. Ltd., Anyang, South Korea; Korea Electric Power Research Institute, Daejeon, South Korea; Chungbuk National University, Chongju, South Korea.

Nucl. Eng. Design, 227, 155-160 . . Effect of Shot Peening on Promary Water Stress Corrosion Cracking of Alloy 600 Steam Generator Tubes in an Operating PWR Plant. . . .Hur, D.H. et al. . . . January 2004. . . KAERI, Daejeon, South Korea; Korea Institute of Nuclear Safety, Daejeon, South Korea; Hanyang University, Seoul, South Korea.

Nucl. Eng. Design, 227, 161-174. . . Formulation of a New Integranular Creep Damage Model for Austenitic Stainless Steels. . . .Michel, B. . . . January 2004. . . CEA Cadarache, St.-Paul-lez-Durance, France.

Nucl. Eng. Design, 227, 175-183. . . Lead Extrusion Dampers for Reducing Seismic Response of Coolant Channel Assembly. . . .Parulekar, Y.M. et al. . . . January 2004. . . Bhabha Atomic Research Centre, Mumbai, India.

Nucl. Eng. Design, 227, 185-193 . . Earthquake Response of Inelastic Structures. . . .Parulekar, Y.M. et al. . . . January 2004. . . Bhabha Atomic Research Centre, Mumbai, India.

Nucl. Eng. Design, 227, 195-207 . . Performance Validation on the Prototype of Control Rod Driving Mechanism for the TRR-II Project. . . .Chyou, Y-P. et al. . . . January 2004. . . Institute of Nuclear Energy Research, Tao-Yuan, Taiwan.

Nucl. Eng. Design, 227, 209-217. . . Lifetime Evaluation of Graphite Components for HTGRs. . . .Oku, T. et al. . . . January 2004. . . University of the Air, Ibaraki-ken, Japan; JAERI, Ibaraki-ken, Japan.

Nucl. Eng. Design, 227, 219-238. . . Investigation on Condensation in Presence of a Noncondensable Gas for a Wide Range of Reynolds Number. . . .Maheshwari, N.K. et al. . . . January 2004. . . Bhabha Atomic Research Centre, Mumbai, India; Tokyo Institute of Technology, Tokyo, Japan.

Nucl. Eng. Design, 227, 239-253 . . Spreading Under Variable Viscosity and Time-Dependent Boundary Conditions: Estimate of Viscosity from Spreading Experiments.. . .Foit, J.J. . . . January 2004. . . Institut fur Kern- und Energietechnik, Karlsruhe, Germany.

Nucl. Eng. Design, 227, 257-271. . . Numerical Prediction of Crack Propagation by an Enhanced Element-Free Galerkin Method.. . .Lee, S-H. et al. . . . February 2004. . . Yonsei University, Seoul, South Korea.

Nucl. Eng. Design, 227, 273-280. . . Effect of Temperature on Graphite Oxidation Behavior. . . .Xiaowei, L. et al. . . . February 2004. . . Tsinghua University, Beijing, China; CEA Cadarache, France.

Nucl. Eng. Design, 227, 281-284. . . Oxidation Behaviour of an HTR Fuel Element Matrix Graphite in Oxygen Compared to a Standard Nuclear Graphite. . . .Moormann, R. et al. . . . February 2004. . . Forschungszentrum Julich, Germany.

Nucl. Eng. Design, 227, 285-300. . . Axial Offset Control of PWR Nuclear Reactor Core Using Intelligent Techniques. . . .Boroushaki, M. et al. . . . February 2004. . . Sharif University of Technology, Tehran, Iran; Tehran University, Tehran, Iran.

Nucl. Eng. Design, 227, 301-312. . . Quasi 3-D Measurements of Turbulence Structure in Horizontal Air-Water Bubbly Flow. . . .Yang, J. et al. . . . February 2004. . . Xi'an Jiaotong University, Shaanxi, PR China.

Nucl. Eng. Design, 227, 313-322. . . Finite Element Analysis of Fluid-Structure Interaction in Pipeline Systems. . . .Sreejith, B. et al. . . . February 2004. . . Indian Institute of Technology Madras, Chennai, India; Indira Gandhi Centre for Atomic Research, Kalpakkam, India.

Nucl. Eng. Design, 227, 323-329 . . Interactions of I2 and CH3I with Reactive Metals Under BWR Severe-Accident Conditions.. . .Glanneskog, H. . . . February 2004. . . Chalmers University of Technology, Goteborg, Sweden.

Nucl. Eng. Design, 227, 331-347. . Inverse Method for Temperature and Stress Monitoring in Complex-Shaped Bodies. . . .Duda, P. et al. . . . February 2004. . . University of Stuttgart, Germany; Cracow University of Technology, Cracow, Poland.

Nucl. Eng. Design, 227, 349-354 . . Reliability of Systems Subject to Common-Cause Hazards. . . .Salem, A.M. et al. . . . February 2004. . . College of Education for Girls, AL-Qassim, Saudi Arabia; Tata University, Tanta, Egypt.

Nucl. Eng. Design, 228, 3-13. . . Short-Term Rupture Studies of Zircaloy-4 and Nb-Modified Zircaloy-4 Tubing Using Closed-End Internal Pressurization. . . .Zhou, Y. et al. . . . March 2004. . . North Carolina State University, Raleigh, NC.

Nucl. Eng. Design, 228, 15-20. . . Dynamic Response Analysis for Fuel Assemblies Under Earthquake and LOCA Accidents. . . .Xie Yongcheng et al. . . . March 2004. . . Shanghai Nuclear Engineering R&D Institute, Shanghai, China.

Nucl. Eng. Design, 228, 21-34. . . Characterization of Neutron Field in the Experimental Fast Reactor JOYO for Fuel and Structural Material Irradiation Test. . . .Aoyama, T. et al. . . . March 2004. . . Japan Nuclear Cycle Development Institute, Ibaraki-ken, Japan.

Nucl. Eng. Design, 228, 35-46. . . Comparative Effects of Structural and Material Parameters Variablity on Pellet-Cladding Interaction in a PWR Fuel Rod. . . .Retel, V. et al. . . . March 2004. . . Universite de Franche-Comte, Besacon, France; EDF, Moret-sur-Loing, France.

Nucl. Eng. Design, 228, 47-54. . . Effects of Irradiation and Deisgn Basis Accident Conditions on Thermal Properties of Epoxy Coating System for Nuclear Power Plant. . . .Park, S-J. et al. . . . March 2004. . . Korea Research Institute of Chemical Technology, Taejon, South Korea.

Nucl. Eng. Design, 228, 55-72. . . Methods for Assessing NPP Containment Pressure Boundary Integrity. . . .Naus, D.J. et al. . . . March 2004. . . Oak Ridge National Laboratory, Oak Ridge, TN; Georgia Institute of Technology, Atlanta, GA; U.S. NRC, Washington, DC.

Nucl. Eng. Design, 228, 73-79. . . Regulatory Strategy for Effective Application of Periodic Safety Review System. . . .Shin, T-M. et al. . . . March 2004. . . Chungju National University, Chungju, South Korea; Korea Institute of Nuclear Safety, Teajon, South Korea.

Nucl. Eng. Design, 228, 81-96. . . Nondestructive Monitoring of Structural Materials Using Automated Ball Indentation (ABI) Technique. . . .Murty, K.L. et al. . . . March 2004. . . North Carolina State University, Raleigh, NC; Indira Gandhi Center for Atomic Research, Kalpakkam, India.

Nucl. Eng. Design, 228, 97-106. . . The Development of Validation Methodology of Multi-Axial Creep Damage Constitutive Equations and Its Application to 0.5Cr0.5Mo0.25V Ferritic Steel at 590 Degrees C.. . .Xu, Q. . . . March 2004. . . The University of Huddersfield, United Kingdom.

Nucl. Eng. Design, 228, 107-117. . . Effect of Axial Restraint on Mechanical Behavior and Average Crack Spacing of Reinforced Concrete Flexural Members. . . .Yi, S-T. et al. . . . March 2004. . . Chung Cheong University, Chungbuk-do, South Korea; Kangnung National University, Kangwon-do, South Korea.

Nucl. Eng. Design, 228, 119-127. . . Strength and Fracture Toughness of Heavy Concrete with Various Iron Aggregate Inclusions. . . .Kan, Y-C. et al. . . . March 2004. . . Chaoyang University of Technology, Taichung County, Taiwan; Institute of Energy Research, Taipei, Taiwan.

Nucl. Eng. Design, 228, 129-142. . . CEA and JNC Approaches for Creep-Fatigue Evaluation of Weldments and Intercomparison Through Benchmark Analyses. . . .Kasahara, N. et al. . . . March 2004. . . Japan Nuclear Cycle Development Institute, Ibaraki-ken, Japan; CEA-Saclay, Gif-sur-Yvette, France.

Nucl. Eng. Design, 228, 143-150. . . Fracture Assessment of a Brittle RPV Under Cold Loading. . . .Sattari-Far, I. et al. . . . March 2004. . . Det Norske Veritas, Stockholm, Sweden.

Nucl. Eng. Design, 228, 151-159. . . Influences of the Dynamic Strain Aging on the J-R Fracture Characteristics of the Ferritic Steels for Reactor Coolant Piping System. . . .Kim, K.C. et al. . . . March 2004. . . Doosan Heavy Industries & Construction Co., Gyeongnam, South Korea.

Nucl. Eng. Design, 228, 161-177. . . Low Cycle Fatigue of Welded Joints: New Experimental Approach. . . .Madi, Y. et al. . . . March 2004. . . Exoles des Mines de Paris, France; Centre d'Etudes de Saclay, Gif-sur-Yvette, France; Lermes-Universite, Aubierre, France.

Nucl. Eng. Design, 228, 179-194. . . Low-Cycle Fatigue of Welded Joints: Coupled Initiation Propagation Model. . . .Madi, Y. et al. . . . March 2004. . . Ecoles des Mines de Paris, France; Lermes-Universite, Aubierre, France; Centre d'Etudes de Saclay, Gif-sur-Yvette, France.

Nucl. Eng. Design, 228, 195-205 . . Safety Evaluation of Rehabilitation of Delaminated Containment Dome. . . .Basu, P.C. et al. . . . March 2004. . . Atomic Energy Regulatory Board, Mumbai, India; University of Mumbai, India.

Nucl. Eng. Design, 228, 207-223. . . Design and Ultimate Behavior of RC Plates and Shells. . . .Min C-S. . . . March 2004. . . Dongguk University, Seoul, South Korea.

Nucl. Eng. Design, 228, 225-244. . . Study on Steel Plate Reinforced Concrete Panels Subjected to Cyclic In-Plane Shear. . . .Ozaki, M. et al. . . . March 2004. . . Kansai Electric Power Co., Osaka, Japan; Japan Atomic Power Co.,Tokyo, Japan; Obayashi Corp., Tokyo, Japan.

Nucl. Eng. Design, 228, 245-259. . . Prediction of Moisture Migration and Pore Pressure Build-Up in Concrete at High Temperatures. . . .Ichikawa, Y. et al. . . . March 2004. . . Kajima Corp., Tokyo, Japan; Imperial College, London, United Kingdom.

Nucl. Eng. Design, 228, 261-272. . . Heat and Mass Transfers in a Concrete Wall with Composite Liner Under Accidental Conditions. . . .Billard, Y. et al. . . . March 2004. . . INSA de Lyon, Villeurbanne, France; EDF/SEPTEN, Villeurbanne, France.

Nucl. Eng. Design, 228, 273-281. . . Sleeve-Type Expansion Anchor Behavior in Cracked and Uncracked Concrete. . . .Kim, S-Y. et al. . . . March 2004. . . Korea Institute of Nuclear Safety, Taejon, South Korea; Korea University, Seoul, South Korea.

Nucl. Eng. Design, 228, 283-304. . . Degradation Assessment of Structures and Passive Components at Nuclear Power Plants. . . .Braverman, J.I. et al. . . . March 2004. . . Brookhaven National Laboratory, Upton, NY; Georgia Institute of Technology, Atlanta, GA; Oak Ridge National Laboratory, Oak Ridge, TN; US NRC, Washington, DC.

Nucl. Eng. Design, 228, 305-317. . . Seismic Analysis of Heavy-Liquid-Metal-Cooled Reactor Vessels. . . .Buongiorno, J. et al. . . . March 2004. . . Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID.

Nucl. Eng. Design, 228, 319-343. . . Investigation Upon the Dynamic Structural Response of a Nuclear Plant on Aseismic Isolating Devices. . . .Micheli, I. et al. . . . March 2004. . . Ansaldo Energia, Genova, Italy; ENEA, Bologna, Italy.

Nucl. Eng. Design, 228, 345-366. . . A NRC-BNL Benchmark Evaluation of Seismic Analysis Methods for Non-Classically Damped Couple Systems. . . .Xu, J. et al. . . . March 2004. . . Brookhaven National Laboratory, Upton, NY; US NRC, Washington, DC.

Nucl. Eng. Design, 228, 367-376. . . Seismic Tests of a Pile-Supported Structure in Liquefiable Sand Using Large-Scale Blast Excitation. . . .Kamijo, N. et al. . . . March 2004. . . Tokyo Electric Power Co., Yokohama, Japan; Kobori Research Complex Inc., Tokyo, Japan; University of Southern California, Los Angeles, CA.

Nucl. Eng. Design, 228, 377-392. . . Seismic Qualification of Expansion Anchors to Canadian Nuclear Standards. . . .Ghobarah, A. et al. . . . March 2004. . . McMaster University, Ontario, Canada; Atomic Energy of Canada L td., Ontario, Canada.

Nucl. Eng. Design, 228, 393-400. . . Safety Analysis of Ulchin Nuclear Power Plant Against Nihonkai-Chubu Earthquake Tsunami.. . .Cho, Y-S., et al. . . . March 2004. . . Hanyang University, Seoul, South Korea; Korea Institute of Nuclear Safety, Daejon, South Korea; National Institute for Disaster Prevention, Seoul, South Korea.

Nucl. Eng. Design, 228, 401-414 . . Simulation of Scaled Vessel Failure Experiments and Investigation of a Possible Vessel Support Against Failure. . . .Willschutz, H.-G. . . . March 2004. . . Institute of Safety Research, Dresden, Germany.

Nucl. Eng. Design, 229, 1-14. . . Analysis of Mechanical Load on Cladding Induced by Fuel Swelling During Power Ramp in High Burn-Up Rod by Fuel Performance Code FEMAXI-6. . . .Suzuki, M. et al. . . . April 2004. . . JAERI, Ibaraki, Japan.

Nucl. Eng. Design, 229, 15-23. . . Application of CANDLE Burnup to Block-Type High Temperature Gas Cooled Reactor. . . .Ohoka, Y. et al. . . . April 2004. . . Tokyo Institute of Technology, Tokyo, Japan.

Nucl. Eng. Design, 229, 25-46. . . Analysis of Natural Circulation Phenomena in VVER-1000. . . .Mousavian, S.K. et al. . . . April 2004. . . Sharif University of Technology, Tehran, Iran; Universita di Pisa, Pisa, Italy.

Nucl. Eng. Design, 229, 47-58. . . An Experimental Investigation on the Critical Heat Flux Enhancement by Mechanical Vibration in Vertical Round Tube. . . .Lee, Y.H. et al. . . . April 2004. . . Korea Advanced Institute of Science and Technology, Daejeon, South Korea.

Nucl. Eng. Design, 229, 59-73. . . The Case of An Oscillating Manometer with Variable Density and Dissipation: Experimental and Numerical Study. . . .Suresan, H. et al. . . . April 2004. . . Indian Institute of Technology, Chennai, India.

Nucl. Eng. Design, 229, 75-80. . . Experimental Thermohydraulic Stability Map of a Freon-12 Boiling Water Reactor Facility with High Exit Friction. . . .de Kruijf, W.J.M. et al. . . . April 2004. . . Delft University of Technology, Delft, The Netherlands.

Nucl. Eng. Design, 229, 81-89. . . A Genetic Algorithm Solution for a Nuclear Power Plant Risk-Cost Maintenance Model. . . .Jiejuan, T. et al. . . . April 2004. . . Tsinghua University, Beijing, PR China.

Nucl. Eng. Design, 229, 91-100. . . Establishment of an Optimal Decontamination Process by the Newly Designed Semi-Pilot Equipment. . . .Kim, K. et al. . . . April 2004. . . KEPRI, Daejon, South Korea; Ebara Industrial Cleaning Co. Ltd., Kawasaki, Japan.

Nucl. Eng. Design, 229, 101-111 . . A Study on a Magnetic Separation of Radioactive Corrosion Products from NPP Using Permanent Magnets. . . .Song, M.C. et al. . . . April 2004. . . Korea Advanced Institute of Science and Technology, Daejeon, Sou th Korea.

Nucl. Sci. Eng. 146, 1-12. . . Experimental Determination of the Ratio of 238U Capture to 235U Fission in LEU-HTR Pebble-Bed Configurations. . . .Koberl, O. et al. . . . January 2004. . . CEA/Cadarache, St.-Paul-lez-Durance, France; Paul Scherrer Institute, Villigen, Switzerland; Institute of Technology, Lausanne, Switzerland.

Nucl. Sci. Eng. 146, 13-50. . Impact of Nuclear Data Uncertainties on Transmutation of Actinides in Accelerator-Driven Assemblies. . . .Aliberti, G. et al. . . . January 2004. . . Argonne National Laboratory, Argonne, IL.

Nucl. Sci. Eng. 146, 51-70. . . Using the Schwinger Variational Functional for the Solution of Inverse Transport Problems. . . .Favorite, J.A. . . . January 2004. . . Los Alamos National Laboratory, Los Alamos, NM.

Nucl. Sci. Eng. 146, 71-87. . . Calculating Nuclear Power Plant Vulnerability Using Integrated Geometry and Event/Fault-Tree Models. . . .Peplow, D.E. et al. . . . January 2004. . . Oak Ridge National Laboratory, Oak Ridge, TN; Defense Threat Reduction Agency, Alexandria, VA.

Nucl. Sci. Eng. 146, 88-98 . . An Order Coding Genetic Algorithm to Optimize Fuel Reloads in a Nuclear Boiling Water Reactor. . . .Ortiz, J.J. et al. . . . January 2004. . . Instituto Nacional de Investigaciones Nucleares, Edo, Mexico; University of Granada, Spain.

Nucl. Sci. Eng. 146, 99-105. . . Slowing-Down Dynamics of Fast Particles in Plasmas via the Fokker-Planck Equation. . . .Anderson, D. et al. . . . January 2004. . . Chalmers University of Technology, Goteborg, Sweden.

Nucl. Sci. Eng. 146, 106-119. . . Calculation and Analysis of n + 112,114-120,122,124,natSn Reactions. . . .Han, Y. . . . January 2004. . . China Institute of Atomic Energy, Beijing, China.

Nucl. Technol., 145, 1-10. . . Monte Carlo Modeling of the Texas A&M University Research Reactor. . . .Kim, C-H. et al. . . . January 2004. . . Hanyang University, Seoul, Korea; Texas A&M University, College Station, TX.

Nucl. Technol., 145, 11-17. . . A Simple and Efficient Control Rod Cusping Model for Three-Dimensional Pin-by-Pin Core Calculations. . . .Yamamoto, A. . . . January 2004. . . Nuclear Fuel Industries, Osaka, Japan.

Nucl. Technol., 145, 18-27. . . Steam Line Break and Station Blackout Transients for Proliferation-Resistant Hexagonal Tight Lattice Boiling Water Reactor. . . .Rohatgi, U.S. et al. . . . January 2004. . . Brookhaven National Laboratory, Upton, NY; Purdue University, West Lafayette, IN.

Nucl. Technol., 145, 28-43 . . Integral Thermal-Hydraulics Tests for the Safety Evaluation of VVER-440/213 Nuclear Reactors and Safety Code Validation. . . .Szabados, L. . . . January 2004. . . KFKI Atomic Energy Research Institute, Budapest, Hungary.

Nucl. Technol., 145, 44-56. . . Feasibility of Increasing the Advanced Test Reactor's Maximum Lobe Power By Adding An Accumulator Injection System. . . .Polkinghorne, S.T. et al. . . . January 2004. . . Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID.

Nucl. Technol., 145, 57-66. . . Thermal Behavior of the Reactor Vessel Penetration Under External Vessel Cooling During a Severe Accident. . . .Kang, K-H. et al. . . . January 2004. . . KAERI, Daejeon, Korea.

Nucl. Technol., 145, 67-81. . . Uranium Transport in a High-Throughput Electrorefiner for EBR-II Blanket Fuel. . . .Ahluwalia, R.K. et al. . . . January 2004. . . Argonne National Laboratory, Argonne, IL.

Nucl. Technol., 145, 82-101. . . Application of Polymers for the Long-Term Storage and Disposal of Low- and Intermediate-Level Radioactive Waste. . . .Bonin, H.W. et al. . . . January 2004. . . Royal Military College of Canada, Ontario, Canada.

Nucl. Technol., 145, 102-114 . . Experimental and Analytical Studies on the Penetration Integrity of the Reactor Vessel Under Extermal Vessel Cooling. . . .Park, R-J. et al. . . . January 2004. . . KAERI, Daejeon, Korea.

Nucl. Technol., 145, 115-137. . . Transient Fuel Behavior and Failure Condition in the CABRI-2 Experiments. . . .Sato, I. et al. . . . January 2004. . . Japan Nuclear Cycle Development Institute, Ibaraki-ken, Japan; Centre d'Etude de Cadarache, St.-Paul-lez-Durance, France; Institut fur Reaktorsicherheit, Karlsruhe, Germany.

Nucl. Sci. Eng. 146, 121-140. . . Variational Variance Reduction for Monte Carlo Eigenvalue and Eigenfunction Problems. . . .Densmore, J.D. et al. . . . February 2004. . . Los Alamos National Laboratory, Los Alamos, NM; University of Michigan, Ann Arbor, MI.

Nucl. Sci. Eng. 146, 141-151 . . An Integral Form of the Variational Nodal Method.. . .Smith, M.A. et al. . . . February 2004. . . Argonne National Laboratory, Argonne, IL; Northwestern University, Evanston, IL; University of Missouri, Rolla, MO.

Nucl. Sci. Eng. 146, 152-175. . . Conditions for a Minimum Critical Mass in a Nuclear Reactor and Considerations on Goertzel's Theorem in Transport Theory. . . .Williams, M.M.R. . . . February 2004. . . Imperial College of Science, London, United Kingdom.

Nucl. Sci. Eng. 146, 176-187. . . A Hybrid Nodal Diffusion/SP3 Method Using One-Node Coarse-Mesh Finite Difference Formulation. . . .Lee, C-H. et al. . . . February 2004. . . Purdue University, West Lafayette, IN.

Nucl. Sci. Eng. 146, 188-199. . . Benchmarking MCNP and WIMS/RFSP Against Measurement Data - I: Deuterium Critical Assembly. . . .Choi, H. et al. . . . February 2004. . . Korea Atomic Energy Research Institute, Taejon, Korea.

Nucl. Sci. Eng. 146, 200-208. . . Measurement of Differential Thick-Target Neutron Yields of C, Al, Ta, W(p,xn) Reactions for 50-MeV Protons. . . .Aoki, T. et al. . . . February 2004. . . Tohoku University, Sendai, Japan.

Nucl. Sci. Eng. 146, 209-220. . . Neutron Capture Cross-Section Measurement of 99Tc by Linac Time-of-Flight Method and the Resonance Analysis. . . .Kobayashi, K. et al. . . . February 2004. . . Kyoto University, Osaka, Japan; Kyushu University, Fukuoka, Japan.

Nucl. Sci. Eng. 146, 221-236. . . Calculation of the Complete Sets of Nuclear Data for n+92,94,96Mo Below 20 MeV. . . .Cai, C. . . . February 2004. . . Nankai University, Tianjin, China.

Nucl. Sci. Eng. 146, 237-244. . . Investigation of the Outgoing Tritons Angular Distribution in the 9Be(nt1y)7Li Reaction at 14.9 MeV by the Line Shape Analysis of the 0.4776-MeV Gamma Transition.. . .Zhou, H. et al. . . . February 2004. . . Beijing Normal University, Beijing, China; A. F. Ioffe Physical-Technical Institute, St. Petersburg, Russia.

Nucl. Sci. Eng. 146, 245-247. . . Accurate Relations Between the Neutron Current Densities and the Neutron Fluxes. . . .Ronen, Y. . . . February 2004. . . Ben-Gurion University of the Negev, Beer-Sheva, Israel.

Nucl. Sci. Eng. 146, 248-255. . . BOT3P - Bologna Transport Analysis Pre-Post-Processors Version 3.0. . . .Orsi, R. . . . February 2004. . . ENEA-FIS-NUC, Bologna, Italy.