The Institute of Nuclear Sciences "Vinca", Physics Laboratory (090) Beograd, Yugoslavia, through the OECD NEA Data Bank, contributed a newly frozen version of FOTELP. The new release FOTELP-2KG, simulates the transport of photons, electrons and positrons by Monte Carlo method for numerical experiments in dosimetry, radiation shielding, and radiotherapy. It can be used for evaluating efficiency of detectors and counters, for computing the absorbed energy in the layers of microelectronics components, for estimating radiation damage of materials, and for other numerical experiments concerning the mentioned particles. Codes from this package perform calculations in 3D geometry with random spectra of particles having energy in the range from 1 keV to 100 MeV and material region for which geometry can be described by planes and surfaces of second order. FOTELP codes apply transition probabilities from the previous to the following state of phase space which are prepared by the included FEPDAT code. Versions of FOTELP and FEPDAT codes for preparation of transition probabilities are described in the User's Manual.
FOTELP-2KG is operable on the VAX or PC. The MicroSoft Fortran compiler (Ver 4.0) can be used to compile the source files under MS-DOS or Windows. RSICC used the Digital Visual Fortran 6.0 compiler to generate executable files under Windows 2000 Professional, and these executables are included in the distribution package. The package is transmitted in a self-extracting, compressed Windows file which contains the documentation, Fortran 77 sources, executables, and test cases. Reference: NET-87 (June 2001). Fortran 77; PC and Vax (C00581/IBMPC/02).
Tokai Research Establishment, Japan Atomic Energy Research Institute, Tokai-mura, Ibaraki-ken, and the O-arai Engineering Center, Japan Nuclear Cycle Development Institute, O-arai-machi, Ibaraki-ken, JAPAN, through the OECD NEA Data Bank in France, contributed this package which includes a modified version of the CCC-371/ORIGEN2.1 code along with the libraries from that package plus new libraries, which are based on current reactor designs using the newest nuclear data file JENDL-3.2 developed in Japan. The libraries contain not only one-grouped cross section data but also variable actinide cross sections and decay and fission yield data. Main objectives of the libraries are to calculate isotopic compositions averaged over whole fuel assemblies for the case of LWR and isotopic compositions averaged over a whole core for the case of FBR. Target fuel assemblies are PWR 17×17 type and BWR 8×8 or 9×9 type. Target core and blanket types of FBR are chosen from several considered specifications. Evaluation of the LWR libraries was conducted by the analysis of latest post irradiation examinations carried out in Japan Atomic Energy Research Institute. The evaluation showed improved results of many isotopes. Evaluation of the FBR libraries was carried out by the comparison between new and old libraries of FBR. The calculated weights of several isotopes presented large differences. The Japanese developers ran the code under SunOS4, Solaris 2.5.1, RedHat Linux 5.2(j), and Compaq Alpha Tru65 Unix 5.0. It was compiled at RSICC under Solaris 2.6, but test cases were not run. The package is transmitted on one CD ROM as a GNU compressed tar file, which includes Fortran source files, data libraries, test cases, and documentation. A Fortran compiler is required to compile the code; no executables are included. This package was erroneously announced in the initial release of our December 2001 Newsletter as DLC-216/ORLIBJ32. References: JAERI-Data/Code 2000-036 (September 2000), JAERI-Data/Code 99-003 (January 2001). Fortran 77; DEC Alpha, Sun, Linux (C00703/MNYWS/00).
Oak Ridge National Laboratory, Oak Ridge, TN, contributed version 15a of MARLOWE, dated September 1, 2001. The new package includes some error corrections for the previous release. It also includes Version 3 of TABULA, a program which uses MARLOWE procedures to tabulate scattering integrals and related data.
MARLOWE is a flexible, comprehensive, and highly portable program for simulating atomic collision processes in crystalline solids with the binary collision approximation. It is used to study phenomena governed by such collisions, including the sizes and shapes of displacement cascades, sputtering, ion ranges, ion reflection, and so on. The program has been used for many years on many different computers and is fully supported on Unix, Linux, and Windows 95/98/ME/NT/2000 systems. Compilers are required on all computers. No executables are included. The GNU f77 compiler can be used on most systems. Fortran 90 and C; Unix and Linux systems; Windows 95/98/NT PCs (P00137/MNYCP/06).
************ DLC-216/ORLIBJ32 ************
This package was erroneously announced
in the initial release of the December 2001 Newsletter as DLC-216/ORLIBJ32.
Because of the inclusion of a modified version of the CCC-371/ORIGEN2.1
code, it will be distributed as a code package. See the CCC-703/ORIGEN-JENDL32
announcement in this same newsletter. We apologize for the confusion
this may cause our users.
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.
Registration information: If
you register by January 31, 2002, you will receive a $100 discount. Cost
of the workshop is $800 registration fee, $125 for the hand-held hard copy
of Slide Rule, $450 for Windows PC version of NCS Slide Rule on CD. For
more information or to register online, go to
PRACTICAL MCNP FOR THE HP, MEDICAL PHYSICIST, AND RAD ENGINEER
DATE: May 6-10, 2002
Monte Carlo type calculations are ideally suited to solving a variety of problems in radiation protection and dosimetry. This course is aimed at the HP, medical physicist, and rad engineer with no prior experience with Monte Carlo techniques. The focus is almost entirely on the application of MCNPTM to solve a variety of practical problems in radiation shielding and dosimetry. The intent is to “jump start” the student toward using MCNPTM productively. Extensive interactive practice sessions are conducted on a personal computer. Topics will include overview of the MCNPTM code and the Monte Carlo method, basic concepts, 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. The course fee includes a complete MCNPTM code package, distributed directly from the Radiation Safety Information Computational Center (RSICC). Students will also 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 ESH-4, MCNP Class/David Seagraves, Mail Stop G761, Los Alamos, NM 87545.
Inquiries regarding registration and class space availability should
be made to David Seagraves, 505-667-3241, fax: 505-665-6071, e-mail: email@example.com.
Technical questions may also be directed to Dick Olsher, 505-667-3364,
The MCNP code developers will
present several classes in 2002 in the United States and two classes in
Europe. The dates for these classes are:
The introductory class is for people who have little or no experience with MCNP. The intermediate to advanced class will be held for people who have used MCNP and want to extend their knowledge and gain depth of understanding.
The classes will be based on MCNP5, that has a tentative release date of April 2002. The code and data package will be available through RSICC at a reduced rate to class participants. The new capabilities of version 5 will be covered.
The other capabilities on MCNP will also be covered, including: Basic geometry and advanced geometry, Source definitions, Tallies, Data, Variance reduction, Statistical analysis, Criticality, Plotting of geometry, tallies, and particle tracks, Neutron/photon/electron physics.
All classes provide interactive
computer learning. 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.
Organizer: Hamilton Quality Consulting
MCNPX is the LANL all-particle,
all-energy (eV-TeV) Monte Carlo transport code based on MCNP4C, LAHET,
CEM, etc. MCNPX has been 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
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.
All 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. Followup consultation for class participants
will be provided.
Classes are taught directly by experienced MCNPX code developers
and instructors. More information on course topics and fees can be found
at the registration website http://mcnpxworkshops.com.
All 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. Followup consultation for class participants will be provided.
Classes are taught directly by experienced MCNPX code developers
and instructors. More information on course topics and fees can be found
at the registration website http://mcnpxworkshops.com.
There is no fee to participate in the meeting, however for planning purposes, advance registration is requested. Everyone, including COSYMA users, are invited to present a paper. Please visit the website www.bnl.gov/est/IMUG2002 to find out about IMUG, register for the meeting or request notification of web updates. The website will be updated as additional information becomes available.
EC-Sponsored Training Course on Radioecological Assessment and Decision-Making Techniques for the Management of Contaminated Freshwater Ecosystems, Jan. 29-Feb. 2, 2002, Madrid, Spain. Sponsored by Polytechnic University of Madrid. Contact: Prof. Alfredo Lorente (tel +34 91 36 3113, then dial ext. 104, fax +34 91 336 3002, email firstname.lastname@example.org).
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).
Thirty-Eighth Annual Meeting of the National Council on Radiation Protection and Measurements,Apr. 10-12, 2002, Arlington, VA. Contact: William M. Beckner (tel 301-657-2652, fax 301-907-8768, url www.ncrp.com).
Back to the Future of Nuclear Technology, 2002 ANS Student Conference, Apr. 10-13, 2002, University Park, PA. Contact: Frank Buschman (tel 814-865-6351, email email@example.com, url www.clubs.psu.edu/ ANS).
12th Biennial RPSD Topical Meeting, Apr. 14-17, 2002, Santa Fe, NM. Hosted by the ANS Trinity Section and cosponsored by the Health Physics Society, L'Organisation de cooperation et de developpement/L'Agence pour l'energie nucleaire (OECD/AEN, and RSICC. Contact: (firstname.lastname@example.org, url www.lanl.gov/ RPSD2002/).
International Youth Nuclear Congress 2002, Apr. 16-20, 2002, Taejon, Korea. Contact: Alexandre Tsiboulia or Han Seong Son (email email@example.com@nanum.kaeri.re.kr url http://www.iync.org).
Seventh International Radiopharmaceutical Dosimetry Symposium, Apr. 17-19, 2002, Nashville, TN. Contact: Michael Stabin (email firstname.lastname@example.org, url http://www.doseinfo-radar.com/symphome.html).
Practical MCNP for the HP, Medical Physicist, and Rad Engineer, May 6-10, 2002, Los Alamos, NM. Contact: David Seagraves (tel 505-667-3241, fax 505-665-6071, email email@example.com, url http://drambuie.lanl.gov/~esh4/mcnp.htm; technical questions to Dick Olsher, 505-667-3365, firstname.lastname@example.org).
Symposium on Radiation Measurements and Applications, May 21-23, 2002, Ann Arbor, MI. Contact: General Chair David K. Wehe (tel 734-764-6215, email email@example.com, url http://rma -symposium.engin.umich.edu/).
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) (email: firstname.lastname@example.org).
Fourth Meeting of the International MACCS Users Group (IMUG) September 6, 2002, in the Principality of Monaco (url www.bnl.gov/est/IMUG2002).
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 http://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, urlwww.aocrp-1.com).
International Conference on
Supercomputing in Nuclear Applications, SNA 2003, September 22-24, 2003,
Paris, France. Organizers: CEA, SFANS, co-organizer: OECD/NEA. (email
SNAemail@example.com, url http://SNA-2003.cea.fr).
Ann. Nucl. Energy, 29, 323-352 . . . Acceleration Techniques for the Characteristic Method in Unstructured Meshes. . . . Santandrea, S.; Sanchez, R. . . . March 2002 . . . Commissariat á l'Energie Atomique, Saclay, France.
Ann. Nucl. Energy, 29, 353-362 . . . Description and Modelling of a Standard Low Level Environmental Radionuclide Calibration Facility. . . . Bakos, G.C. . . . March 2002 . . . Democritus University of Thrace, Xanthi, Greece.
Ann. Nucl. Energy, 29, 363-384 . . . Parameter Sensitivities in Nuclear Reaction Cross-Section Calculations. . . . Fessler, A.; Smith, D.L. . . . March 2002 . . . Argonne National Laboratory, Argonne, IL.
Ann. Nucl. Energy, 29, 385-414 . . . On Galanin's Constant in the Source-Sink Method. . . . Williams, M.M.R. . . . March 2002.
Ann. Nucl. Energy, 29, 415-428 . . . Variation of Transmitted Particle Flux with Strength of Forward and Backward Scattering in Deep Penetration Problems. . . . Sahni, D.C.; Sjöstrand, N.G. . . . March 2002 . . . Bhabha Atomic Research Centre, Bombay, India; Chalmers University Technology, Göteborg, Sweden.
Ann. Nucl. Energy, 29, 429-446 . . . Transfer Pathways of 54Mn, 57Co, 85Sr, 103Ru and 134Cs in Rice and Radish Plants Directly Contaminated at Different Growth Stages. . . . Choi, Y.H.; Lim, K.M.; Yu, D.; Park, H.G.; Choi, Y.G.; Lee, C.M. . . . March 2002 . . . Korea Atomic Energy Research Institute, Taejon, South Korea.
Ann. Nucl. Energy, 29, 447-463 . . . An Integrated Knowledge Base Development Tool for Knowledge Acquisition and Verification for NPP Dynamic Alarm Processing Systems. . . . Park, J.H.; Seong, P.H. . . . March 2002 . . . Korea Atomic Energy Research Institute, Taejon, South Korea; KAIST, Taejon, South Korea.
Ann. Nucl. Energy, 29, 465-475 . . . Potential Impacts to Operating Nuclear Power Plants Due to Application of Revised Source Term. . . . Moon, J-H.; Kang, C-S. . . . March 2002 . . . Seoul National University, Republic of Korea.
Ann. Nucl. Energy, 29, 477-488 . . . Effect of Coolant Channel Width on Group Constants and Multiplication Factor of Research Reactors Using MTR Type Low Enriched Uranium Fuel. . . . Ahmad, A.N. . . . March 2002 . . . Pakistan Institute of Engineering and Applied Sciences, Islamabad, Pakistan.
Ann. Nucl. Energy, 29, 489-490 . . . Book Review: Nuclear Power. . . . Henderson, H. . . . March 2002.
Eng. Fail. Anal., 9, 1-15 . . . Aircraft Landing Gear Failure: Fracture of the Outer Cylinder Lug. . . . Azevedo, C.R.F.; Hippert, E. Jr.; Spera, G.; Gerardi, P. . . . February 2002 . . . Laboratory for Failure Analysis, São Paulo, Brazil.
Eng. Fail. Anal., 9, 17-30 . . . Failure Analysis of Cracking at Volute Tongues of Feedwater Pump Casings. . . . Kim, J.W.; Kim, Y.S.; Park, C.Y. . . . February 2002 . . . Korea Electric Power Research Institute, Taejon, South Korea.
Eng. Fail. Anal., 9, 31-43 . . . Hot Corrosion in Gas Turbine Components. . . . Eliaz, N.; Shemesh, G.; Latanision, R.M. . . . February 2002 . . . Massachusetts Institute of Technology, Cambridge, MA; Israel Air Force, Israel.
Eng. Fail. Anal., 9, 45-61 . . . Fatigue Lives for Induction Hardened Shafts with Subsurface Crack Initiation. . . . Tjernberg, A. . . . February 2002 . . . Volvo Construction Equipment Components AB, Eskilstuna, Sweden.
Eng. Fail. Anal., 9, 63-76 . . . Thermal Cracking in Disk Brakes. . . . Mackin, T.J. et al. . . . February 2002 . . . The University of Illinois at Urbana-Champaign, Urbana, IL.
Eng. Fail. Anal., 9, 77-82 . . . Investigation of Fracture in a K12 Tongue Component. . . . Sudhakar, K.V. . . . February 2002 . . . Central Michigan University, Mount Pleasant, MI.
Eng. Fail. Anal., 9, 83-92 . . . Remnant Life Assessment of Service-Exposed Pendent. . . . Ray, A.K. et al. . . . February 2002 . . . National Metallurgical Laboratory, Bihar, India.
Eng. Fail. Anal., 9, 93-97 . . . Formation of a Crater in the Workpiece on an Electrical Discharge Machine. . . . Bojorquez, B.; Marloth, R.T.; Es-Said, O.S. . . . February 2002 . . . Loyola Marymount University, Los Angeles, CA.
Eng. Fail. Anal., 9, 99-107 . . . Alternative Heat Treatments for A357-T6 Aluminum Alloy. . . . Es-Said, O.S. et al. . . . February 2002 . . . Loyola Marymount University, Los Angeles, CA.
Eng. Fail. Anal., 9, 109-122 . . . Fatigue Damage Leads to a Serious Traffic Accident. . . . Otegui, J.L. . . . February 2002 . . . University of Mar del Plata, Mar del Plata, Argentina.
J. Nucl. Mater., 299, 1-8 . . . Analysis of Singular Interface Stresses in Dissimilar Material Joints for Plasma Facing Components. . . . You, J.H.; Bolt, H. . . . October 2001 . . . Max-Planck-Institut fur Plasmaphysik, Garching, Germany.
J. Nucl. Mater., 299, 9-19 . . . Analytical Method for Thermal Stress Analysis of Plasma Facing Materials. . . . You, J.H.; Bolt, H. . . . October 2001 . . . Max-Planck-Institut fur Plasmaphysik, Garching, Germany.
J. Nucl. Mater., 299, 20-27 . . . The Effect of the Point Defects on the Behavior of a Crack Inside of a Pressure Tube. . . . Sarce, A. . . . October 2001 . . . Comisión Nacional de Energía Atómica, Buenos Aires, Argentina.
J. Nucl. Mater., 299, 28-31 . . . Heat Capacity Measurements on BaThO3 and BaCeO3. . . . Krishnan, R.V.; Nagarajan, K.; Rao, P.R.V. . . . October 2001 . . . Indira Gandhi Centre for Atomic Research, Tamilnadu, India.
J. Nucl. Mater., 299, 32-42 . . . Behavior of Plutonium and Americium at Liquid Cadmium Cathode in Molten LiCl-KCl Electrolyte. . . . Iizuka, M. et al. . . . October 2001 . . . Central Research Institute of Electric Power Industry, Tokyo, Japan; JAERI, Ibaraki, Japan.
J. Nucl. Mater., 299, 43-52 . . . Study of Mechanisms Involved in Thermal Migration of Molybdenum and Rhenium in Apatites. . . . Gaillard, C. et al. . . . October 2001 . . . Université Claude Bernard, Villeurbanne, France; CEA/DRCP/SCPS/LCAM, Bagnols-sur-Cèze, France; Institut de Recherche sur la Catalyse, Villeubanne, France; Institut National des Sciences Appliquées, Villeurbanne, France.
J. Nucl. Mater., 299, 53-67 . . . Modeling of Microstructure Evolution in Austenitic Stainless Steels Irradiated Under Light Water Reactor Condition. . . . Gan, J.; Was, G.S.; Stoller, R.E. . . . October 2001 . . . Pacific Northwest National Laboratory, Richland, WA; University of Michigan, Ann Arbor, MI; Oak Ridge National Laboratory, Oak Ridge, TN.
J. Nucl. Mater., 299, 68-76 . . . Effect of Ensemble of Stress Concentrators on the Ultimate Tensile Strength of Material. . . . Voskobionikov, R.E. . . . October 2001 . . . Kurchatov Institute, Moscow, Russia.
J. Nucl. Mater., 299, 77-82 . . . A Novel Technique to Remove Deuterium from CANDU Pressure Tubes. . . . Qin, Z.; Zhang, C.-S.; Griffiths, K.; Norton, P.R. . . . October 2001 . . . University of Western Ontario, Canada.
J. Nucl. Mater., 299, 83-89 . . . Effect of Helium Implantation on Mechanical Properties and Microstructure Evolution of Reduced-Activation 9Cr-2W Martensitic Steel. . . . Kasada, R.; Morimura, T.; Hasegawa, A.; Kimura, A. . . . October 2001 . . . Kyoto University, Kyoto, Japan; Tohoku University, Sendai, Japan.
J. Nucl. Mater., 299, 91-100 . . . Microstructure and Properties of a Cu-Cr-Zr Alloy. . . . Batra, I.S.; Dey, G.K.; Kulkarni, U.D.; Banerjee, S. . . . November 2001 . . . Bhabha Atomic Research Centre, Mumbai, India.
J. Nucl. Mater., 299, 101-110 . . . 3D Micromechanical Modeling of Packed Beds. . . . Lu, Z.; Abdou, M.; Ying, A. . . . November 2001 . . . University of California - Los Angeles, CA.
J. Nucl. Mater., 299, 111-123 . . . Effect of the Expansion Associated with the Plutonium -- Phase Transitions on Storage Can Integrity. . . . Spearing D.R.; Veirs, D.K.; Prenger, F.C. . . . November 2001 . . . Los Alamos National Laboratory, Los Alamos, NM.
J. Nucl. Mater., 299, 124-131 . . . Blister Formation of Tungsten Due to Ion Bombardment. . . . Wang, W.; Roth, J.; Lindig, S.; Wu, C.H. . . . November 2001 . . . Max-Planck-Institut für Plasmaphysik, Garching, Germany; Shanghai Institute of Nuclear Research, China.
J. Nucl. Mater., 299, 132-139 . . . Fracture Behavior of Heat-Affected Zone in Low Alloy Steels. . . . Kim, J.H.; Oh, Y.J.; Hwang, I.S.; Kim, D.J.; Kim, J.T. . . . November 2001 . . . Seoul National University, South Korea; Doo-San Heavy Industries and Construction Co., Ltd., Kyungnam, South Korea.
J. Nucl. Mater., 299, 140-147 . . . Computer Simulation of Pu3+ and Pu4+ Substitutions in Gadolinium Zirconate. . . . Williford, R.E.; Weber, W.J. . . . November 2001 . . . Pacific Northwest National Laboratory, Richland, WA.
J. Nucl. Mater., 299, 148-156 . . . Varying Temperature Irradiation Experiment in HFIR . . . Muroga, T.; Zinkle, S.J.; Qualls, A.L.; Watanabe, H. . . . November 2001 . . .National Institute for Fusion Science, Gifu, Japan; Oak Ridge National Laboratory, Oak Ridge, TN; Kyushu University, Fukuoka, Japan.
J. Nucl. Mater., 299, 157-164 . . . Microstructure-Fracture Toughness Relationship of Vanadium Alloy/Stainless Steel Brazed Joints. . . . Gan, Y.X.; Aglan, H.A.; Steward, R.V.; Chin, B.A.; Grossbeck, M.L. . . . November 2001 . . . Tuskegee University, Tuskegee, AL; Auburn University, Auburn, AL; Oak Ridge National Laboratory, Oak Ridge, TN.
J. Nucl. Mater., 299, 165-170 . . . Thermodynamic Stability of Solid SrThO3. . . . Ali(Basu), M.; Mishra, R.; Bharadwaj, S.R.; Kerkar, A.S.; Dharwadkar, S.R.; Das, D. . . . November 2001 . . . Bhabha Atomic Research Centre, Mumbai, India; The Institute of Science, Mumbai, India.
J. Nucl. Mater., 299, 171-174 . . . On the Relationship Among "f" Texture Factors for the Principal Planes of Zirconium, Hafnium and Titanium Alloys. . . . Kearns, J.J. . . . November 2001.
J. Nucl. Mater., 299, 175-179 . . . Irradiation Behavior of U-Nb-Zr Alloy Dispersed in Aluminum. . . . Meyer, M.K.; Hofman, G.L.; Wiencek, T.C.; Hayes, S.L.; Snelgrove, J.L. . . . November 2001 . . . Argonne National Laboratory-West, Idaho Falls, ID; Argonne National Laboratory-East, Argonne, IL.
Nucl. Eng. Des., 208, 221-234 . . . Tensile and Stress Corrosion Cracking Properties of Type 304 Stainless Steel Irradiated to a Very High Dose. . . . Chung, H.M.; Strain, R.V.; Shack, W.J. . . . September 2001 . . . Argonne National Laboratory, Argonne, IL.
Nucl. Eng. Des., 208, 235-244 . . . Consequence Calculation for Relocation After Nuclear Accidents. . . . Qu, J. . . . September 2001 . . . Tsinghua University, Beijing, China.
Nucl. Eng. Des., 208, 245-254 . . . Power Up-Grading Study for the First Egyptian Research Reactor. . . . Temraz, H.E.; Ashoub, N.; Fathallah, A. . . . September 2001 . . . National Center for Nuclear Safety and Radiation Control, Cairo, Egypt; Atomic Energy Authority, Cairo, Egypt.
Nucl. Eng. Des., 208, 255-263 . . . The Effect of High Pressure Test Look (HPTL) on the Reactivity of ET-RR-2 Reactor. . . . Ashoub, N. . . . September 2001 . . . Atomic Energy Authority, Cairo, Egypt.
Nucl. Eng. Des., 208, 265-282 . . . Coupled Thermal Structural Analysis of LWR Vessel Creep Failure Experiments. . . . Willschütz, H.-G.; Altstadt, E.; Sehgal, B.R.; Weiss, F.-P. . . . September 2001 . . . Institute of Safety Research, Dresden, Germany; Royal Institute of Technology, Stockholm, Sweden.
Nucl. Eng. Des., 208, 283-303 . . . Experimental Studies on Rewetting of Hot Vertical Annular Channel. . . . Saxena, A.K.; Rarj, V.V.; Rao, V.G. . . . September 2001 . . . Bhabha Atomic Research Centre, Mumbai, India; Indian Institute of Technology, Mumbai, India.
Nucl. Eng. Des., 208, 305-313 . . . Safety Criteria and Quality Control of HTTR Fuel. . . . Sawa, K.; Suzuki, S.; Shiozawa, S. . . . September 2001 . . . JAERI, Ibaraki-ken, Japan.
Nucl. Technol., 136, 141-157 . . . Studies on the Comprehensive Methodology for Structuring Accident Mitigation Systems for Next-Generation Pressurized Water Reactors. . . . Tsujikura, Y. . . . November 2001 . . . Kansai Electric Power Company, Osaka, Japan.
Nucl. Technol., 136, 158-168 . . . A Statistical Approach to Predict the Failure Enthalpy and Reliability of Irradiated PWR Fuel Rods During Reactivity-Initiated Accidents. . . . Nam, C.; Jeong, Y-H.; Jung, Y-H. . . . November 2001 . . . KAERI, Daejon, Korea.
Nucl. Technol., 136, 186-196 . . . Thermal-Hydraulic Simulation of Localized Flow Characteristics in a Steam Generator. . . . Ferng, Y-M.; Ma, Y-P.; Kang, J-C. . . . November 2001 . . . Institute of Nuclear Energy Research, Lungtan, Taiwan; Taiwan Power Co., Taiwan.
Nucl. Technol., 136, 197-203 . . . A New Method to Determine the Neutron Sensitivity of a Micro Fission Chamber for a Boiling Water Reactor. . . . Kimura, A. et al. . . . November 2001 . . . University of Tokyo, Japan; Toshiba Corp., Yokohama, Japan.
Nucl. Technol., 136, 204-220 . . . Safety Evaluation of Primary-Side Bleed-and-Feed Scenarios by an Experimental Loss of Feedwater Event at the IIST Facility. . . . Liu, T-J.; Chiang, S-C. . . . November 2001 . . . Institute of Nuclear Energy Research, Lungtan, Taiwan; Taiwan Power Co., Taipei, Taiwan.
Nucl. Technol., 136, 231-240 . . . Radiolysis of Bicarbonate and Carbonate Aqueous Solutions: Product Analysis and Simulation of Radiolytic Processes. . . . Cai, Z.; Li, X.; Katsumura, Y.; Urabe, O. . . . November 2001 . . . University of Tokyo, Japan.
Nucl. Technol., 136, 241-254 . . . Void Fraction Measurement in Subcooled-Boiling Flow Using High-Frame-Rate Neutron Radiography. . . . Kureta, M.; Akimo, H.; Hibiki, T.; Mishima, K. . . . November 2001 . . . JAERI, Ibaraki, Japan; Kyoto University Research Reactor Institute, Osaka, Japan.