Radiation Safety Information Computational Center
	Oak Ridge National Laboratory Post Office Box 2008 Oak Ridge, Tennessee 37831-6362 Managed by UT-Battelle, LLC for the U.S. Department of Energy under contract DE-AC05-00OR22725 Phone No. 865-574-6176 FAX 865-574-6182 Internet: PDC@ORNL.GOV WWW: http://www-rsicc.ornl.gov/rsic.html
No. 437	July 2001
"A society grows great when old men plant trees whose shade they know they shall never sit in." -- Greek Proverb

• New for 2002
• RSICC Welcomes Dr. Shyam Joshi
• 2001 Distinguished Scientific Achievement Award
• CHANGES TO THE COMPUTER CODE and DATA COLLECTION
• CONFERENCES, COURSES, SYMPOSIA
• Visual Editor Classes Offered
• MCNP Introductory Workshop
• SCALE Training Course Schedule
• Advanced Training Course on PENELOPE-2000
• Seventh International Radiopharmaceutical Dosimetry Symposium
• Calendar
• JUNE ACCESSION OF LITERATURE

The objective of ACES is to enhance contact between less experienced contractors and highly experienced nuclear code experts. This is a cooperative agreement to satisfy NRC; DOE NN, NE, DP; and DOD sponsors' needs for nuclear model/code/data consultations. ACES goals are:

• Guide users toward higher quality work,
• Faster solutions to users' code work problems,
• Enable efficient and effective use of codes,
• Guide users through code limitations or bugs,
• Save sponsors significant time and money,
• Working with users to provide experienced nuclear replacement staff - Nuclear Skills Retention Measures - CHILES COMMISSION

Dr. Joshi is a tenured Associate Professor in Mechanical Engineering at Southern University, Baton Rouge, Louisiana. He is also Adjunct Associate Professor at Louisiana State University, Baton Rouge, Louisiana, in the Department of Industrial and Manufacturing Systems Engineering. Dr. Joshi's teaching and research interests cover the areas of manufacturing/materials/design/control with emphasis on modeling, sensing, and control of manufacturing processes, automation, robotics and machine vision, metrology, vibration-based condition monitoring, statistical signal processing, industrial simulation, and integration of design and manufacturing. He has published over 30 refereed papers in his areas of expertise. He serves as a reviewer for five engineering journals, NSF, and is a member of two journal editorial boards. Dr. Joshi participated in several research and curriculum enhancement projects funded by grants from NSF, NIST, NASA, and Louisiana Board of Regents. His active research grants include a $50,000 award from Proctor & Gamble Company for "Manufacturing Processes" curriculum development. He will be with RSICC until August 31, 2001.
 

Many people know John H. Hubbell's name, because it is associated with dosimetry data that health physicists use all the time. John joined the staff of the National Bureau of Standards (now known as NIST) in 1950 and spent his professional career there, directing the NBS/NIST X-Ray and Ionizing Radiation Data Center from 1963 to 1981. His collection and critical evaluation of experimental and theoretical photon cross section data resulted in the development of tables of attenuation and energy-absorption coefficients, as well as related quantities such as atomic form factors, incoherent scattering functions, atomic photoeffect, and pair and triplet production cross sections. John's most widely known work is National Standard Reference Data Series Report 29: Photon Cross Sections, Attenuation Coefficients, and Energy Absorption Coefficients from 10 keV to 100 GeV. John has published extensively during his career. So useful and important are these contributions that no less than three of his publications have been named "Citation Classics" by the Institute for Scientific Information, as evidence of their numerous citations in other papers. One of the pieces of work in which he still takes great pride is the first analytical solution to the Rectangular Source problem, now called the Hubbell Rectangular Source Integral, published in the NBS Journal of Research in 1960. John technically retired from NIST in 1988, but continues to actively contribute to the organization as a Radiation Physics Consultant.

John is a Fellow of both the Health Physics Society (HPS) and the American Nuclear Society (ANS). His awards include the Faculty Medal from the Technical University of Prague, the Paul C. Aebersold Award from the Society of Nuclear Medicine, the ANS Radiation Industry Award, the ANS Professional Excellence Award, the University of Michigan Dept. of Nuclear Engineering Outstanding Alumnus Award, and a Doctor Honoris Causa from the University of Cordoba, Argentina, Faculty of Mathematics, Astronomy and Physics.
 

J. Stewart Bland Associates, Inc., Annapolis, Maryland, contributed a corrected version of this suite of NRC's computer codes used for evaluating routine radioactive effluents from nuclear power plants with a WINDOWS interface to facilitate ease of use. An indexing problem with the XOQDOQ code that causes the deposition values to be incorrectly calculated was fixed, and a printing problem exhibited on the Windows 98 operating system was corrected. All users are advised to update to the corrected version. NRCDose includes LADTAP II, GASPAR II, and XOQDOQ. It is intended for modeling routine, normal effluents under annual average environmental conditions and should not be used for accident dose assessment.

NRCDose runs on IBM PC Pentium type computers. The distributed executables were created with the Microsoft Fortran PowerStation (Standard Edition) Version 4.0 under the Windows operating system. Fortran source files are not included. The codes were tested under Windows 95, Windows 98, Windows NT 4.0. The package is transmitted on CD with a Windows install procedure. References: User's Guide, (November 14, 2000); NUREG/CR-4653, PNL-5907 (March 1987); NUREG/CR-1276, ORNL/NUREG/TDMC-1 (March 17, 1980); NUREG/CR-2919 (PNL-4380) (September 1982). Fortran; Pentium (C000684PC58601).
 
 

Los Alamos National Laboratory, Los Alamos, New Mexico, contributed a modified version of this automated, multi-step Monte Carlo burnup code system to calculate coupled neutronic/isotopic results for nuclear systems. MONTEBURNS is a fully automated tool that links the Monte Carlo transport code CCC-700/MCNP4C with the radioactive decay and burnup code CCC-371 /ORIGEN2.1. This release works with MCNP4A, MCNP4B, and MCNP4C. Some minor changes were made, but no new features were added in this release. MONTEBURNS produces a large number of criticality and burnup results based on various material feed/removal specifications, power(s), and time intervals. The principle function is to transfer one-group cross-section and flux values from MCNP to ORIGEN2, and then transfer the resulting material compositions (after irradiation and/or decay) from ORIGEN2 back to MCNP in a repeated, cyclic fashion (a simple predictor-corrector method is used during this process).

The code runs on Sun Solaris and Windows NT systems. Note that it does not run under Windows95 or 98. The main part of the code was written in Fortran 77; but the interface between MCNP, ORIGEN2, and monteb is a Perl script that runs the codes and processes intermediate data. Note that MCNP, ORIGEN2.1 and Perl are not included in this package. Reports: LA-UR-99-4999 (September 1999). Fortran 77 and Perl; Unix Sun and PC NT systems; possibly also Unix HP and VMS systems (P00455MNYCP01).
 
 

Lawrence Livermore National Laboratory, Livermore, California, contributed this temperature dependent ENDF/B-VI, Release 7, cross section library called POINT2000. ENDF/B-VI, Release 7 completely supersedes all preceding releases of ENDF. As distributed, the data include cross sections represented in the form of a combination of resonance parameters and/or tabulated energy dependent cross sections, nominally at 0 Kelvin temperature. For use in applications this library has been processed into the form of temperature dependent cross sections at eight temperatures between 0 and 2100 Kelvin, in steps of 300 Kelvin. At each temperature the cross sections are tabulated and linearly interpolable in energy. Many changes were made in ENDF/B-VI evaluation between the last version of this library (POINT97), which was based on release 4 data, and the current version (POINT2000), which is based on release 7 data. Details of these changes are in UCRL-ID-12776-Rev-1, which is included with the package.

This library contains all of the evaluations in the ENDF/B-VI general purpose library, which contains evaluations for 324 materials (isotopes or naturally occurring elemental mixtures of isotopes). This library does not contain data from special purpose ENDF/B-VI libraries, such as fission products, thermal scattering, photon interaction data.

The majority of these evaluations are complete, in the sense that they include all cross sections over the energy range 10-5 eV to at least 20 MeV. However, the following are only partial evaluations that either only contain single reactions and no total cross section (Mg24, K41, Ti46, Ti47, Ti48, Ti50 and Ni59), or do not include energy dependent cross sections above the resonance region (Ar40, Mo92, Mo98, Mo100, In115, Sn120, Sn122 and Sn124).

The package is transmitted on three CDs which includes the referenced documents, the entire library in the computer independent ENDF/B-VI character format, which allows the data to be easily transported between computers. Approximately 1.6 gigabyte of storage is required for all the data. Reference: UCRL-ID-12776-Rev-1 (November 22, 2000). ASCII data; PC or Workstation (D00212MNYCP00).
 
 

The Department of Health Physics, Tokai Research Establishment, JAERI, Tokai, Ibaraki, Japan, contributed these nuclear decay data files for radiation dosimetry calculations. The DECDC decay data were prepared using decay data sets from the Evaluated Nuclear Structure Data Files (ENSDF), the latest version in August 1997. Basic nuclear properties in the decay data sets were examined and updated by referring to NUBASE, the database for nuclear and decay properties of nuclides, and by using the utility programs of ENSDF. The revised data sets were processed by EDISTR in order to calculate the energies and intensities of particles, particles, rays, internal conversion electrons, X rays, and Auger electron emitted in nuclear transformation. The compiled data were prepared in two different types of format: Publ. 38 and NUCDECAY formats. The DECDC data package is based on more recent nuclear data than DLC-172/NucDecay. The libraries are transmitted in a self-extracting WinZip file on CD-ROM. The uncompressed ASCII data files (1037 files) are about 70 MB. References: JAERI-Data/Code 2001-004, March 2001, JAERI-Data/Code 99-035, July 1999. ASCII format, IBM PC, UNIX Workstation (D00213MNYCP00).
 

Every attempt is made to ensure that the links provided in the Conference and Calendar sections of this newsletter are correct and live. However, the very nature of the web creates the possibility that the links may become unavailable. In that case, please call or mail the contact provided.
 

Display MCNP 4C geometries in multiple plot windows.
Create surfaces and cells to build a geometry.
Create materials using the local xsdir file.
Store commonly used materials in a material library.
Sub-divide large cells into smaller cells.
Full geometry capabilities including universes and lattices.
Interactively set cell importances from the plot window.
Display source points and collision points in the plot window.

A four-day class will be held August 20-24, 2001, in Richland, Washington. This class will include an overview of MCNP along with training on the use of the MCNP visual editor.

A three-day class is to be held October 8-10, 2001, in Richland, Washington. This class will only focus on the use of the visual editor. For the three-day class, users should already be familiar with the use of MCNP.

Both classes will include computer demonstrations and exercises that 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 the Linux operating system and Windows NT. Class attendees can use either the Linux or Windows version of the visual editor. Attendees are encouraged to bring their own input files for viewing and modifying in the visual editor. Further information on both classes can be located at: www.mcnpvised.com, or by contacting Randy Schwarz (email randyschwarz@mcnpvised.com).
 

Another Monte Carlo N-Particle Transport Code Workshop will be held August 14-17, 2001.  This introductory class is taught by the team who develops and maintains MCNP.

The class is for people who have little or no experience with MCNP. The class surveys the features of MCNP so the beginning user will be exposed to the capabilities of the program, and will have hands-on experience at running the code to solve rudimentary problems. Course topics include Basic Geometry, Source Definitions, Output (Tallies) Specification and Interpretation, Advanced Geometry (repeated structures specification), Variance Reduction Techniques, Statistical Analysis, Criticality, Plotting of Geometry, Tallies, and Particle Tracks, and Neutron/Photon/Electron Physics.

Costs For Domestic U.S. Class: Cost for the class is $1,800. There is a $300 discount if payment is received by the close of registration/early payment deadline for each class. Radiation Safety Information Computational Center (RSICC) provides the code and data package and documentation for a reduced fee of $450 to all who complete the class and free to students employed by sponsors that fund RSICC.

 The class fee includes a notebook with all class viewgraphs (over 300) and handouts. Dinner the first evening is included as part of your registration fee and snacks and refreshments are provided during class breaks.  Lodging will be available for roughly $75 per night. Information will be sent by follow-up letter or email when we receive your registration information.

 The class provides interactive computer learning. Time will be available to discuss individual questions and problems with MCNP experts. To register for the LANL class via the Internet, go to http://www.solutionsbyhqc.com/mcnpform.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. Classes are cosponsored by RSICC. Foreign nationals must register at least six weeks in advance. For further information, contact Kay at 865-574-9213 or visit the web, http://www.cped.ornl.gov/scale/trcourse.html.

The SCALE Shielding and Source Terms Course emphasizes SAS2 and ORIGEN-ARP (depletion/source-term generation) and SAS3 and SAS4 using MORSE-SGC (3-D Monte Carlo neutron/gamma shielding). It also covers SAS1/XSDRNPM (1-D neutron/gamma shielding) and QADS/QAD-CGGP (3-D point kernel gamma shielding).

The SCALE KENO V.a Criticality Course focuses on KENO V.a and the associated criticality analysis sequences in CSAS. KENO V.a is a widely used 3-D multigroup Monte Carlo criticality safety analysis code that has been in use for approximately 15 years. It is a fast, easy-to-use code that allows users to build complex geometry models using basic geometrical bodies of cuboids, spheres, cylinders, hemispheres, and hemicylinders. Two-dimensional color plots of the geometry model can be generated.
 

If you are interested in participating, please send the completed form on the web site by the end of July 2001. The course will be taught by the code authors F. Salvat, J.M. Fernandez-Varea, and J. Sempau.

PENELOPE performs Monte Carlo simulation of coupled electron-photon transport in arbitrary materials. A mixed procedure is used for the simulation of electron and positron interactions (elastic scattering, inelastic scattering and bremsstrahlung emission), in which 'hard' events (i.e. those with deflection angle and/or energy loss larger than pre-selected cutoffs) are simulated in a detailed way, while 'soft' interactions are calculated from multiple scattering approaches. Photon interactions (Rayleigh scattering, Compton scattering, photoelectric effect and electron-positron pair production) are simulated in a detailed way.
 

All announcements and other mailings for this meeting will be done electronically (no paper mail will be sent). A call for abstracts (also electronic) will go out in a few months, with authors notified of outcome in approximately October of this year. Contributors will be required to bring an electronic version of their manuscript to the meeting in April 2002; early plans are to have the proceedings published as a supplement to the Journal of Nuclear Medicine. You can contact Michael Stabin (michael.g.stabin@vanderbilt.edu) if you have questions.
 

Monte Carlo Analysis, Aug. 13-17, 2001, Knoxville, TN, a short course by the Univ. of Tennessee. Contact: Kristin England, Univ. of Tennessee, Knoxville (tel 865-974-5048, email utne@tennessee.edu, url www.engr.utk.edu/dept/nuclear/TIW.html).

Nuclear Criticality Safety, Aug. 13-17, 2001, Knoxville, TN, a short course by the Univ. of Tennessee. Contact: Kristin England, Univ. of Tennessee, Knoxville (tel 865-974-5048, email utne@tennessee.edu, url www.engr.utk.edu/dept/nuclear/TIW.html).

U.S. Women in Nuclear, Aug. 19-21, 2001, St. Petersburg Beach, FL, sponsored by the Nuclear Energy Institute. Contact: Katie Hart, NEI (tel 202-739-8077, fax 202-785-4019, email kgh@nei.org; url www.nei.org).
Visual Editor Class, Aug. 20-24, 2001, Richland, WA. Contact: Randy Schwarz (email randyschwarz@mcnpvised.com, url www.mcnpvised.com).

September 2001

International Conference on Topical Issues in Nuclear Safety, Sept. 3-6, 2001, Vienna, Austria, sponsored by the International Atomic Energy Agency. Contact: IAEA (tel +43-1-2600-21270, fax +43-1-2600-29610, email official.mail@iaea.org, url www.iaea.org).

13th International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 2001), Sept. 3-7, 2001, Chicago, IL, sponsored by the U.S. Dept. of Energy. Contact Institute of Nuclear Materials Management (tel 847-480-6342, fax 847-480-9282, email rairth@patram.com, url www.patram.org).

GLOBAL-2001: International Conference on the Back-End of the Fuel Cycle: From Research to Solutions, Sept. 9-13, 2001, Paris, France. Co-sponsored by OECD/NEA. Contact: (email global2001@cea.fr , url www.cea.fr/conferences/global2001/ index.htm).

M&C 2001 Annual Meeting - Special Session: Variance Reduction for Monte Carlo Criticality Simulations, Sept. 9-13, 2001, Salt Lake City, UT. Contact: Dr. Bojan Petrovic, (tel 412-256-1295, fax 412-256-2444, email PetrovB@westinghouse.com, url www.srv.net/~ians/MC2001).

M&C 2001 - International Meeting on Mathematical Methods for Nuclear Applications, Sept. 9-13, 2001, Salt Lake City, UT. Contact: Jeff Borkowski, technical program chair (tel 208-522-1060, fax 208-522-1187, email jeff@soa.com, url www.srv.net/~ians/MC2001/).

Second International Conference on Inertial Fusion Science and Applications (IFSA '01), Sept. 10-14, 2001, Kyoto, Japan, sponsored by the Institute of Laser Engineering and others, and cosponsored by ANS. Contact: ILE (email ifsa01@ile.osaka-u.ac.jp, url www.ile.osaka-u.ac.jp/ifsa2001/top.html).

Eighth International Conference on Radioactive Waste Management and Environmental Remediation (ICEM '01), Sept. 30-Oct. 4, 2001, Bruges, Belgium, sponsored by the American Society of Mechanical Engineers and others. Contact: Donna McComb, (tel 520-292-5652, fax 520-292-9080, email dmccomb@laser-options.com, url www.icemcomf.com).

October 2001

7th Annual Workshop on Monte Carlo Simulation of Radiotherapy Treatment Sources Using the OMEGA/BEAM Code System, Oct. 1-4, 2001, National Research Council of Canada, Ottawa, Canada. Contact: Blake Walters (tel 613-993-2715, fax 613-952-9865, e-mail bwalters@irs.phy.nrc.ca, url www.irs.inms.nrc.ca/inms/irs/BEAM/beamhome.html).

Nuclear Data for Science and Technology, Embracing the Future at the Beginning of the 21st Century, Oct. 7-12, 2001, Tsukuba, Japan. Sponsored by JAERI, co-sponsored by OECD/Nuclear Energy Agency and Atomic Energy Society of Japan. Contact My Associates, Inc. (tel +81-3-3422-8584, fax +81-3-3422-7534, email myasso@ad.il24.net).

The XIX Autumn School on New Perspectives with Nuclear Radioactivity, Oct. 8-13, 2001, Libson, Portugal. Contact: Ms. Sandra Oliveira (tel +351-21-8419092, fax +351-21-8419143, email nrad2001@cfif.ist.utl.pt).

Visual Editor Class, Oct. 8-10, 2001, Richland, WA. Contact: Randy Schwarz (email randyschwarz@mcnpvised.com, url www.mcnpvised.com).

November 2001

Actinides Conference, Nov. 4-9, 2001, Hayama, Japan. Contact: Dr. T. Ogawa, Secretary for Actinides-2001 (fax +81 29 282 5922, email actq@act2001.tokai.jaeri.go.jp, url act2001.tokai.jaeri.go.jp/).

ANS Nuclear Criticality Safety Division Embedded Topical Meeting "Practical Implementation of Nuclear Criticality Safety," Nov. 11-15, 2001, Reno, NV. Contact: (email topical@ncsd.ans.org; url, ncsd.ans.org/topical/).

ANS Winter Meeting, Gathering and Technical Sessions in Memory of Dr. Allan F. Henry (1935-2001), Nov. 11-14, 2001, Reno, NV. These are special sessions, and refreshments will be served. Contact: Kord Smith (email kord@soa.com,url www.ans.org/meetings/).

The 5th KEK Topical Conference - Frontiers in Flavor Physics, Nov. 20-22, 2001, KEK, Tsukuba, Japan. Contact: Dr. Sakue Yamada, Chairman (email kektc5@kek.jp, url kektc5.kek.jp).

Advanced Training Course on PENELOPE-2000 - Physics, Code Structure and Operation, 3-day course date to be announced later, Paris, France. Contact: Enrico Sartori (tel +33 1 45 24 10 72 or 78, fax +33 1 45 24 11 10 or 28, email sartori@nea.fr, url www.nea.fr/html/dbprog/penelope2001-1.html).

March 2002

Hardened Electronics and Radiation Technology (HEART) Conference, Mar. 11-15, 2002, Monterey, CA. Contact: Thomas Stringer, chair (tel 719-599-1719, fax 719-599-1991).

April 2002

Seventh International Radiopharmaceutical Dosimetry Symposium, April 17-19, 2002, Nashville, TN. Contact: Michael Stabin (email michael.g.stabin@vanderbilt.edu).

June 2002

Topical Meeting: Industrial Radiation and Radioisotope Measurement Applications IRRMA-V A Class IV Topical, June 9-14, 2002, Bologna, Italy, co-sponsored by the American Nuclear Society. Contact: Prof. Jorge Fernandez (Chair) (e-mail: jorge.fernandez@mail.ing.unibo.it).

October 2002

PHYSOR 2002, Oct. 7-10, 2002, Seoul, Korea, sponsored by the American Nuclear Society and hosted by the Korean Nuclear Society. Contact: Prof. Nam Zin Cho (tel +82-42-869-3819, fax +82-42-869-5859, email tpc@physor2002.kaist.ac.kr, url physor2002.kaist.ac.kr).

First Asian and Oceanic Congress for Radiation Protection (AOCRP-1), Oct. 20-24, 2002, Seoul, Korea, sponsored by the Korean Association for Radiation Protection (KARP). Contact: Dr. Myung-Jae SONG (tel +82-42-870-0202, fax +82-42-870-0269, email mjsong@khnp.co.kr; url www.aocrp-1.com).

Ann. Nucl. Energy, 28, 1155 . . . Nuclear Reactor Theory in Canada 1943-1956. . . . Williams, M.M.R. . . . August 2001.

Ann. Nucl. Energy, 28, 1157-1173 . . . Capture of Neutrons by Cylindrical Absorbing Rods Placed Around A Pile. . . . Fell, J.M.G.; Volkoff, G. . . . August 2001 . . . National Research Council of Canada, Montreal, Canada.

Ann. Nucl. Energy, 28, 1175-1192 . . . Measurement of Activation Cross-Sections for (n,2n) Reactions Producing Short-Lived Nuclei in the Energy Range Between 13.4 and 14.9 MeV. . . . Sakane, H.; Kasugai, Y.; Shibata, M.; Iida, T.; Takahashi, A.; Fukahori, T.; Kawade, K. . . . August 2001 . . . Nagoya University, Nagoya, Japan; Osaka University, Osaka, Japan; Japan Atomic Energy Research Institute, Ibaraki-ken, Japan.

Ann. Nucl. Energy, 28, 1193-1217 . . . HGPT Based Sensitivity Time-Dependent Methods for the Analysis of Subcritical Systems. . . . Gandini, A. . . . August 2001 . . . University of Rome, Rome, Italy.

Ann. Nucl. Energy, 28, 1219-1235 . . . Application of a Reduced Order Model to BWR Corewide Stability Analysis. . . . Cecenas-Falcon, M.; Edwards, R.M. . . . August 2001 . . . Instituto de Investigaciones Electricas, Mor, Mexico; Pennsylvania State University, University Park, PA.

Ann. Nucl. Energy, 28, 1237-1250 . . . An Assessment Methodology for In-Vessel Corium Retention by External Reactor Vessel Cooling During Severe Accidents in PWRs. . . . Park, J.H.; Jeong, Y.H.; Baek, W-P.; Chang, S.H. . . . August 2001 . . . Korea Institute of Nuclear Safety, Taejon, South Korea; Korea Advanced Institute of Science and Technology, Taejon, South Korea.

Ann. Nucl. Energy, 28, 1251-1267 . . . A Preconditioned Krylov Method for Solution of the Multi-Dimensional, Two Fluid Hydrodynamics Equations. . . . Downar, T.J.; Joo, H.G. . . . August 2001 . . . Purdue University, W. Lafayette, IN; Korea Atomic Energy Research Institute, Taejon, South Korea.

J. Nucl. Mater., 295, 1-15 . . . Effect of Bonding and Bakeout Thermal Cycles on the Properties of Copper Alloys Irradiated at 350C. . . . Singh, B.N.; Edwards, D.J.; Eldrup, M.; Toft, P. . . . May 2001 . . . Riso National Laboratory, Roskilde, Denmark; Pacific Northwest National Laboratory, Richland, WA.

J. Nucl. Mater., 295, 16-20 . . . Embrittlement Behaviour of Different International Low Activation Alloys After Neutron Irradiation. . . . Schneider, H.-C.; Dafferner, B.; Aktaa, J. . . . May 2001 . . . Forschungszentrum Karlsruhe, Karlsruhe, Germany.

J. Nucl. Mater., 295, 21-26 . . . Ductility and Strain Rate Sensitivity of Zircaloy-4 Nuclear Fuel Claddings. . . . Lee, K.W.; Kim, S.K.; Kim, K.T.; Hong, S.I. . . . May 2001 . . . Chungnam National University, Taejon, South Korea; KEPCO Nuclear Fuel Co., Ltd., Taejon, South Korea.

J. Nucl. Mater., 295, 27-30 . . . Permeation Behavior of Deuterium Implanted in Electro- and Sputter-Deposited Copper Coatings on Aluminum Alloy Substrates. . . . Alam, M.; Inal, M.Y. . . . May 2001 . . . New Mexico Institute of Mining and Technology, Socorro, NM.

J. Nucl. Mater., 295, 31-41 . . . Effect of Mo Addition on the Crystal Texture and Deformation Twin Formation in Zr-Based Alloys. . . . Chun, Y.B.; Hwang, S.K.; Kim, M.H.; Kwun, S.I.; Chae, S.W. . . . May 2001 . . . Inha University, Incheon, South Korea; Center for the Advanced Aerospace Materials, South Korea; Korea University, Seoul, South Korea.

J. Nucl. Mater., 295, 42-48 . . . Oxidation and Its Effects on the Mechanical Properties of Nb-1Zr. . . . DiStefano, J.R.; Chitwood, L.D. . . . May 2001 . . . Oak Ridge National Laboratory, Oak Ridge, TN.

J. Nucl. Mater., 295, 49-56 . . . Hydrogen Isotope Diffusive Transport Parameters in Pure Polycrystalline Tungsten. . . . Esteban, G.A.; Perujo, A.; Sedano, L.A.; Douglas, K. . . . May 2001 . . . European Commission Joint Research Center, Ispra, Italy.

J. Nucl. Mater., 295, 57-63 . . . Estimation of the Standard Entropies of Some Am(III) and Cm(III) Compounds. . . . Konings, R.J.M. . . . May 2001 . . . European Commission, Karlsruhe, Germany.

J. Nucl. Mater., 295, 64-72 . . . Vitrification of Gamma Irradiated ⁶⁰Co²+ Zeolites. . . . Bulbulian, S.; Bosch, P. . . . May 2001 . . . Instituto Nacional de Investigaciones Nucleares A.P.; Mexico DF, Mexico; Unversidad Autonoma Metropolitana, Mexico DF, Mexico.

J. Nucl. Mater., 295, 73-82 . . . Pore Migration in UO₂ and Grain Growth Kinetics. . . . Bourgeois, L.; Dehaudt, Ph.; Lemaignan, C.; Fredric, J.P. . . . May 2001 . . . Commissariat a l'Energie Atomique, Grenoble, France.

J. Nucl. Mater., 295, 83-96 . . . SON 68 Nuclear Glass Alteration Kinetics Between pH 7 and pH 11.5. . . . Gin, S.; Mestre, J.P. . . . May 2001 . . . Commissariat a l'Energie Atomique (CEA), Bagnols-sur-Ceze, France.

J. Nucl. Mater., 295, 97-108 . . . Oxidation of Zircaloy-2 and Zircaloy-4 in Water and Lithiated Water at 360C. . . . Oskarsson, M.; Ahlberg, E.; Pettersson, K. . . . May 2001 . . . Royal Institute of Technology, Stockholm, Sweden; Goteborg University, Goteborg, Sweden.

J. Nucl. Mater., 295, 109-120 . . . Hydrogen Concentrations Near Cracks in Target Materials for High-Power Spallation Neutron Sources. . . . Rauh, H.; Ullmaier, H. . . . May 2001 . . . Technische Universitat Darmstadt, Darmstadt, Germany; Institut fur Festkorperforschung, Julich, Germany.

J. Nucl. Mater., 295, 121-125 . . . Phase Transformation of Polycrystalline Zirconia Induced by Swift Heavy Ion Irradiation. . . . Gibert-Mougel, C.; Couvreur, F.; Costantini, J.M.; Bouffard, S.; Levesque, F.; Hemon, S.; Pa . . . May 2001 . . . CEA Saclay, Gif-sur-Yvette, France; CIRIL, Caen, France; LERMAT, Caen, France.

J. Nucl. Mater., 295, 126-130 . . . Phase Transformation of Stabilised Zirconia in Water and 1.0 M LiOH. . . . Oskarsson, M.; Ahlberg, E.; Pettersson, K. . . . May 2001 . . . Royal Institute of Technology, Stockholm, Sweden, Goteborg University, Goteborg, Sweden.

J. Nucl. Mater., 295, 131 . . . Erratum to 'Properties and Radiation Effects in High-Temperature Pyrolzed PIP-SiC/SiC' [J. Nucl. Mater. 289 (2001) 42-47]. . . . Katoh, Y.; Kotani, M.; Kishimoto, H.; Yang, W.; Kohyama, A. . . . May 2001 . . . Kyoto University, Kyoto, Japan; CREST, Saitama, Japan.

J. Nucl. Mater., 295, 132 . . . Erratum to 'Molecular Dynamics Refinement of Topologically Generated Reconstructions of Simulated Irradiation Cascades in Silica Networks' [J. Nucl. Mater. 289 (2001) 71-79] . . . Yuan, X.; Pulim, V.; Hobbs, L.W. . . . May 2001 . . . Massachussetts Institute of Technology, Cambridge, MA.

Nucl. Eng. Des., 207, 11-19 . . . AMBIDEXTER Nuclear Energy Complex: A Practicable Approach for Rekindling Nuclear Energy Application. . . . Oh, S.K.; Chung, K.M. . . . July 2001 . . . Ajou University, Suwon, South Korea.

Nucl. Eng. Des., 207, 21-31 . . . Study on the Natural Circulation Characteristics of the Integral Type Reactor for Vertical and Inclined Conditions. . . . Kim, J-H.; Kim, T-W.; Lee, S-M.; Park, G-C. . . . July 2001 . . . Seoul National University, Seoul, South Korea.

Nucl. Eng. Des., 207, 33-40 . . . Cooling Elements for Passive Heat Removal. . . . Warnke, E.P.; Kanzleiter, T.F.; Hicken, E.F.; Dreier, J. . . . July 2001 . . . Siempelkamp Guss- und Anlagentechnik, Krefeld, Germany; Battelle Ingenieurtechnik, Eschborn, Germany; Forschungszentrum, Julich, Germany; Paul-Scherrer-Institut, Villingen, Switzerland.

Nucl. Eng. Des., 207, 41-48 . . . System Improvements and New Experiments in the Advanced Test Reactor, Idaho National Engineering and Environmental Laboratory. . . . Furstenau, R.V.; Mecham, D.C. . . . July 2001 . . . US Department of Energy, Idaho Falls, ID; Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID.

Nucl. Eng. Des., 207, 49-57 . . . EPR Accident Scenarios and Provisions. . . . Bittermann, D.; Krugmann, U.; Azarian, G. . . . July 2001 . . . Framatome ANP, Erlangen, Germany; Framatome ANP, Paris-La-Defense, France.

Nucl. Eng. Des., 207, 59-64 . . . The OBE Elimination in Piping Design. . . . Cho, H-C.; Kim, I-Y.; Yun, S-C.; Park, K-W. . . . July 2001 . . . Korea Power Engineering Co., Inc., Kyunggi-Do, South Korea.

Nucl. Eng. Des., 207, 65-76 . . . A Study on the Connection Effects of Subsurface Slabs to Exterior Walls in the KNGR Seismic Analysis. . . . Jang, Y-S.; Kim, T-Y. . . . July 2001 . . . Korea Power Engineering Co., Inc.; Kyunggi, South Korea.

Nucl. Eng. Des., 207, 77-93 . . . Dynamic Characteristics and Structural Response of the SWR 1000 Under Earthquake Loading Conditions. . . . Bielor, E.; Brettschuh, W.; Krutzik, N.J.; Tropp, R. . . . July 2001 . . . Siemens Nuclear Power, Offenbach, Germany.

Nucl. Eng. Des., 207, 95-104 . . . Defense-in-Depth and Diversity Evaluation to Cope with Design Bases Events Concurrent with Common Mode Failure in Digital Plant Protection System for KNGR. . . . Shin, L.C.; Park, C.E.; Jin, C.C.; Tae, S.J. . . . July 2001 . . . Korea Power Engineering Co., Inc., Taejon, South Korea.

Nucl. Eng. Des., 207, 105-119 . . . Development of Advanced I&C in Nuclear Power Plants: ADIOS and ASICS. . . . Kim, J-T.; Kwon, K-C.; Hwang, I-K.; Lee, D-Y.; Park, W-M.; Kim, J-S.; Lee, S-J. . . . July 2001 . . . Korea Atomic Energy Research Institute, Taejon, South Korea; Chungnam National University, Chungnam, South Korea.

Grenoble Report 01.45 . . . Origen of Light Nuclei in Near Earth Orbit. . . . Derome, L.; Buenerd, M. . . . 2001 . . . Institut des Sciences Nucleaires, Grenoble, France.

ORNL-tr-5234 . . . Theoretical and Experimental Tests of the Natural Convection in the Core of Pebble Bed High Temperature Reactors. . . . Schuerenkraemer, M. . . . April 1984 . . . Institut fuer Reaktorentwicklung, Juelich, Germany. . . . . . . Translation by: the Language Center, Pittsburgh, PA.