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:
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,
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
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
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
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.
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
by contacting Randy Schwarz (email firstname.lastname@example.org).
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.NOTE: While MCNP supports a number of platforms, class computers are usually Unix machines. Experience with Unix will be helpful to the student but is not essential.
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.
SCALE Shielding and Source Terms Course (October 15-19, 2001)
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).
SCALE KENO-Va Criticality Course (October 22-26, 2001)
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
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
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 (email@example.com)
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 firstname.lastname@example.org, 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 email@example.com, 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 firstname.lastname@example.org; url www.nei.org).
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 email@example.com, 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 firstname.lastname@example.org, 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 email@example.com , 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 firstname.lastname@example.org, 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 email@example.com, 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 firstname.lastname@example.org, url www.icemcomf.com).
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 email@example.com, 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 firstname.lastname@example.org).
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 email@example.com).
ANS Nuclear Criticality Safety Division Embedded Topical Meeting "Practical Implementation of Nuclear Criticality Safety," Nov. 11-15, 2001, Reno, NV. Contact: (email firstname.lastname@example.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 email@example.com,url www.ans.org/meetings/).
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 firstname.lastname@example.org, url www.nea.fr/html/dbprog/penelope2001-1.html).
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).
Seventh International Radiopharmaceutical Dosimetry Symposium, April 17-19, 2002, Nashville, TN. Contact: Michael Stabin (email email@example.com).
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: firstname.lastname@example.org).
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 email@example.com, 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 firstname.lastname@example.org; url www.aocrp-1.com).
Nuclear Systems Literature (Shielding, Safety, Materials)
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.