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 http://www-rsicc.ornl.gov/rsic.html
No. 440	October 2001
"Nothing can stop the man with the right attitude from achieving his goal; and nothing on earth can help the man with the wrong attitude. -- W.W. Ziege

• September 11, 2001
• MCNP Forum Archives
• ANST WWW Site on Web
• NRC Codes Made Available
• CHANGES TO THE COMPUTER CODE and DATA COLLECTION
• CONFERENCES, COURSES, SYMPOSIA
• Symposium on Radiation Measurements and Applications
• MCNPX Classes for 2002
• MACCS Meeting
• Advanced Training Course on PENELOPE-2000
• Seventh International Radiopharmaceutical Dosimetry Symposium
• Calendar
• SEPTEMBER ACCESSION OF LITERATURE

The RSICC staff wishes to express its sadness and prayers to those directly affected by the tremendous loss due to the terrorist events in NYC, Washington, and Pennsylvania, September 11, 2001. Staff scattered on travel were immediately contacted and have safely returned. Thank you for the many condolences we have received from around the world.

Taken from ORNL Today, 09/17/01....ORNL remains in a state of heightened security after last week's terrorist activity in Washington and New York. Last Thursday, the folks in Bldg. 6011 hung flags out of all windows on the front side of the building, "in honor of victims, rescuers, and the whole country."

Taken from Washington Post, 09/17/01 …Everyone in the coming months is going to need this capacity of holding more than one thing in mind, of balancing conflicting feelings. Americans were confronted last week by an act of unspeakable hatred for their country, but they also were touched by signs of solidarity and affection and respect around the world. They were shaken by an unprecedented sense of vulnerability, but they also watched as their Congress and executive branch rose to the occasion with firmness and no panic. They felt helpless, but moved forthwith to offer help.

As RSICC staff move into FY02, we will be here to continue to serve the national safety interests in Nuclear Nonproliferation, Defense Programs, and Naval Reactors areas.

DLC-061/KDDK
CCC-365/IODES
CCC-692/TOXRISK
PSR-469/WREM--TOODEE2--MOD3
PSR-486/TSORT

CHANGES TO THE COMPUTER CODE and DATA COLLECTION

Lawrence Livermore National Laboratory, Livermore, California, contributed a newly frozen version of this coupled neutron-photon Monte Carlo transport code system designed to use three dimensional (3-D) combinatorial geometry. Neutron and/or photon sources as well as neutron induced photon production can be tracked. It is a complete system to assist with input preparation, running Monte Carlo calculations, and analysis of output results. TART2000 is also incredibly FAST; if you have used similar codes, you will be amazed at how fast this code is compared to other similar codes. Use of the entire system can save you a great deal of time and energy.

TART2000 extends the general utility of the code to even more areas of application than available in previous releases, by concentrating on improving the physics, particularly with regard to improved treatment of neutron fission, resonance self-shielding, molecular binding, and extending input options used by the code. TART2000 uses the latest ENDF/B-VI, Release 7, data. TART2000 is now distributed only with 650 group ENDF/B-VI neutron interaction data; support of the older 175 group ENDL data has now been dropped. Several utilities are included for creating input files and displaying TART results and data. TART2000 completely supersedes all older versions of TART, and it is strongly recommended that one use only the most recent version of TART2000 and its data files.

TART2000 runs on Cray, Unix workstations (Sun, SGI, HP, DEC-Alpha, Meiko, IBM, etc.), IBM-PC (Windows and Linux) and Power MAC. For use on IBM-PC and Power MAC, the entire system is distributed in executable form, so that no compiler or loader is required. The ABSOFT Fortran compiler was used to create PC executables, which run under 32-bit systems. On all other computers, a Fortran compiler which supports Cray-like pointers is required.

The package is distributed on CD in both Windows and UNIX formats. The CD contains the documentation, source codes for Unix systems, PC executables, data files and test cases for use on a variety of computers. References: UCRL-ID 126455, Rev. 3 (November 2000). Fortran 77; Cray, Unix workstations (Sun, SGI, HP, DEC-Alpha, Meiko, IBM, etc.), IBM-PC (Windows or Linux) and Power MAC (C00638/MNYCP/04).
 
 

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. The new release corrects runtime errors in GASPAR and XOQDOQ modules of the 2.3.1 version. All users are advised to update to the corrected version. RSICC mailed the new release to recipients of the previous release. 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 in DOS format. 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 (C00684/PC586/02).
 
 

Jozef Stefan Institute, Ljubljana, Slovenia, through the OECD Nuclear Energy Agency Data Bank, Issy-les-Moulineaux, France, contributed this code system to calculate mixed cores in TRIGA Mark II research reactors. TRIGLAV can be applied for fuel element burn-up calculations, for power and flux distributions calculations and for reactivity predictions. The WIMS-D4 program with the original WIMS cross-section library extended for TRIGA reactor specific nuclides is required. TRIGLAV is based on four group, time-independent diffusion equations in two dimensional cylindrical (r, theta) geometries. The diffusion equation is solved using finite differences method with iteration of fission density.

TRIGLAV runs under the MS-DOS and Linux operating systems. The included Windows PC executables were created with Lahey F77L3-EM/32 Version 5. the package is transmitted on CD in a self-extracting, compressed Windows file. References: IJS-DP-7862, Version 1 (March 28, 2000) and IJS-DP-6242 (March 2000). Fortran 77; PC (P00495/PC586/00).
 
 

The Technical University of Budapest Institute of Nuclear Techniques, Budapest, Hungary, and Delft University of Technology Interfaculty Reactor Institute Mekelweg, Delft, The Netherlands, through the Nuclear Energy Agency Data Bank, Issy-les-Moulineaux, France, contributed DANCOFF-MC. This program calculates by Monte Carlo method the Dancoff factor which can be used to determine the flux reduction in resonance integral calculations. DANCOFF-MC allows almost arbitrary arrangement of cylindrical or spherical fuel elements: different fuel region diameters, clads and gaps with different sizes, annular rods, arbitrary positions of rods or spherical pellets, and different macroscopic cross sections for each fuel element and its clad. Optionally, it is also possible to calculate the Dancoff factor in a lattice of "grey", i.e., partially transparent, fuel lumps.

DANCOFF-MC runs on DEC Alpha, Sun and Pentium computers. A Fortran 90 compiler is required to run DANCOFF-MC under Unix. The Lahey F95 V5.6 compiler was used to create the PC executables which are included in the package. The executables can be run in a DOS window of Windows95, WindowsNT or better. The codes were also compiled and test cases executed on PC with the Lahey F90 V4.0 compiler and on DEC Alpha and Sun workstations with Fortran 90 compilers. The package is transmitted on a CD which contains a self-extracting compressed Windows file with source files, PC executables, scripts, test cases and information files. Reference: IRI-131-95-003 (June 1997). Fortran 90; Unix workstations and PC (P00509/MNYCP/00).

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.
 

First call for papers: deadline for receipt of summaries is January 23, 2002. For more information see the website at: http://rma-symposium.engin.umich.edu/ or contact David K. Wehe at dkw@umich.edu.
 
 

MCNPX is the LANL all-particle, all-energy (eV-GeV) Monte Carlo transport code based on MCNP4C2, LAHET, CEM, etc. MCNPX has been developed for the past six years, particularly for the high-energy accelerator community, and has now become an accepted tool for a broad range of applications by nuclear engineers, physicists, and scientists. All workshops are hands-on and will include a distribution of MCNPX 2.3 (subject to participant export approval), LA150 (150 MeV) cross-section data, and a notebook of viewgraphs. More information on course topics and fees can be found at the registration web site.
 
 

There is no fee to participate in the meeting. Advance registration is requested, for planning purposes. 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.
 

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). Abstracts (also electronic) are being accepted until September 30, 2001, with authors notified of outcome in approximately October. 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. The web site is http://www.doseinfo-radar.com/symphome.html.
 
 

MCNPX Intermediate Workshop, October 22-26, 2001, Knoxville, TN. Contact Bill Hamilton (tel (505) 662-9097, email registrar@mcnpxworkshops.com, url http://mcnpxworkshops.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 http://act2001.tokai.jaeri.go.jp/).

Decontamination and Decommissioning of Research Reactors and Other Small Nuclear Facilities Training Course, Nov. 5-9, 2001, Augusta, GA. Contact: Larry E. Boing (tel 630-252-6729, fax 630-252-5287, email lboing@anl.gov, url http://www.td.anl.gov/D&D/).

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, http://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 http://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 http://kektc5.kek.jp).

Advanced Training Course on PENELOPE-2000 - Physics, Code Structure and Operation, Nov. 5-7, 2001, 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 http://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

MCNPX Intermediate Workshop, April 9-12, 2002, Santa Fe/Los Alamos, NM. Contact Bill Hamilton (tel (505) 662-9097, email registrar@mcnpxworkshops.com, url http://mcnpxworkshops.com).

Thirty-Eight 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 fxb129@psu.edu, 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: (email rpsd2002@lanl. gov, url www.lanl.gov/ RPSD2002/).

International Youth Nuclear Congress 2002, Apr. 16-20, 2002, Taejon, Korea. Contact: Alexandre Tsiboulia or Han Seong Son (email alexts@ippe.obninsk.ru, hsson@nanum.kaeri.re.kr, url http://www.iync.org).

Seventh International Radiopharmaceutical Dosimetry Symposium, Apr. 17-19, 2002, Nashville, TN. Contact: Michael Stabin (email michael.g.stabin@vanderbilt.edu, url http://www.doseinfo-radar.com/symphome.html).

May 2002

MCNPX Introductory Workshop, May 13-17, 2002 Los Alamos, NM. Contact Bill Hamilton (tel (505) 662-9097, email registrar@ mcnpxworkshops.com, url http://mcnpxworkshops.com).

Symposium on Radiation Measurements and Applications, May 21-23, 2002, Ann Arbor, MI. Contact: General Chair David K. Wehe (tel 734-764-6215, email dkw@umich.edu, url http://rma -symposium.engin.umich.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)

MCNPX Intermediate Workshop Lisbon, June 24-28, 2002, Lisbon, Portugal. Contact Bill Hamilton (tel (505) 662-9097, email registrar@ mcnpxworkshops.com, url http://mcnpxworkshops.com).

September 2002

Fourth Meeting of the International MACCS Users Group (IMUG) September 6, 2002, in the Principality of Monaco (url www.bnl.gov/est/IMUG2002).

YUNSC 2002 - The 4th International Conference of Yugoslav Nuclear Society, Sept.30-Oct.3, 2002, Belgrade, Yugoslavia. (Contact info: email yuns@rt270.vin.bg.ac.yu, url http://www.vin.bg.ac.yu/YUNS).

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 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 mjsong@khnp.co.kr; url www.aocrp-1.com).

September 2003

International Conference on Supercomputing in Nuclear Applications, SNA 2003, September 22-24, 2003, Paris, France. Organizers: CEA, SFANS, co-organizer: OECD/NEA. (email SNA-2003@cea.fr, url http://SNA-2003.cea.fr).
 
 

J. Nucl. Mater., 297, 231-243 . . . Determination of Dissolution Rates of Spent Fuel in Carbonate Solutions Under Different Redox Conditions with a Flow-Through Experiment. . . . Röllin, S.; Spahiu, K.; Eklund, U.-B. . . . September 2001 . . . Studsvik Nuclear AB, Nyköping, Sweden; SKB, Stockholm, Sweden.

J. Nucl. Mater., 297, 244-250 . . . Nuclear Microphobe Analysis of ⁷Li Profile Induced in HfB₂ by a Neutron Irradiation. . . . Simeone, D.; Deschanels, X.; Gosset, D.; Bonal, J.P.; Berthoumieux, E. . . . September 2001 . . . CEA, Gif-sur-Yvette, France.

J. Nucl. Mater., 297, 251-261 . . . Irradiation Effects on Toughness Behaviour and Microstructure of VVER-Type Pressure Vessel Steels. . . . Böhmert, J.; Viehrig, H.-W.; Ulbricht, A. . . . September 2001 . . . Forschungszentrum Rossendorf, Dresden, Germany.

J. Nucl. Mater., 297, 262-270 . . . Effect of Point Defect Interaction with Bubble Surface on the Nucleation and Growth of Gas Bubbles. . . . Voskoboinikov, R.E.; Volkov, A.E. . . . September 2001 . . . Kurchatov Institute, Moscow, Russia.

J. Nucl. Mater., 297, 271-278 . . . Comparative Analysis of Pressure Vessel Integrity for Various LOCA Conditions. . . . Çolak, Ü.; Özdere, O. . . . September 2001 . . . Hacettepe University, Ankara, Turkey; Turkish Atomic Energy Agency, Ankara, Turkey.

J. Nucl. Mater., 297, 279-284 . . . Response of Reduced Activation Ferritic Steels to High-Fluence Ion-Irradiation. . . . Tanigawa, H. et al. . . . September 2001 . . . JAERI, Ibaraki, Japan; Kyoto University, Kyoto, Japan; The University of Tokyo, Ibaraki, Japan.

J. Nucl. Mater., 297, 285-291 . . . Tritium Permeation Behavior Implanted into Pure Tungsten and Its Isotope Effect. . . . Nakamura, H. et al. . . . September 2001 . . . JAERI, Ibaraki-ken, Japan.

J. Nucl. Mater., 297, 292-302 . . . Precipitation of Reoriented Hydrides and Textural Change of -Zirconium Grains During Delayed Hydride Cracking of Zr-2.5%Nb Pressure Tube. . . . Kim, Y.S.; Perlovich, Y.; Isaenkova, M.; Kim, S.S.; Cheong, Y.M. . . . September 2001 . . . Korea Atomic Energy Research Institute, Taejon, Republic of Korea.

J. Nucl. Mater., 297, 303-312 . . . EXAFS/XANES Studies of Plutonium-Loaded Sodalite/Glass Waste Forms. . . . Richmann, M.K.; Reed, D.T.; Kropf, A.J.; Aase, S.B.; Lewis, M.A. . . . September 2001 . . . Argonne National Laboratory, Argonne, IL.

J. Nucl. Mater., 297, 313-326 . . . Factors Governing Microstructure Development of Cr2O3-Doped UO2 During Sintering. . . . Bourgeois, L.; Dehaudt, Ph.; Lemaignan, C.; Hammou, A. . . . September 2001 . . . Commissariat à l'Energie Atomique, Grenoble, France; Université Joseph Fourier de Grenoble, France.

J. Nucl. Mater., 297, 327-331 . . . Effect of a Trivalent Dopant, Gd³⁺, on the Oxidation of Uranium Dioxide. . . . Kim, J-G.; Ha, Y-K.; Park, S-D.; Jee, K-Y.; Kim, W-H. . . . September 2001 . . . KAERI, Taejon, Korea.

J. Nucl. Mater., 297, 332-340 . . . Thermodynamics of the UO₂ Solid Solution with Magnesium and Europium Oxides. . . . Funjino, T. et al. . . . September 2001 . . . Tohoku University, Sendai, Japan; JAERI, Ibaraki-ken, Japan.

J. Nucl. Mater., 297, 341-344 . . . The Study of Microstructural Defects and Mechanical Properties in Proton-Irradiated Zr-1.0%Nb-1.0%Sn-0.1%Fe. . . . Mukherjee, P. et al. . . . September 2001 . . . Variable Energy Cyclotron Centre, Calcutta, India; Saha Institute of Nuclear Physics, Calcutta, India; Bhabha Atomic Research Centre, Mumbai, India; Regional Engineering College, Durgapur, India; Jadavpur University, Calcutta, India.

J. Nucl. Mater., 297, 345-354 . . . Temperature Effects on the Radiation Stability and Ion Exchange Capacity of Smectites. . . . Gu, B.X.; Wang, L.M.; Minc, L.D.; Ewing, R.C. . . . September 2001 . . . University of Michigan, Ann Arbor, MI.

J. Nucl. Mater., 297, 355-357 . . . Accumulation and Recovery of Defects in Ion-Irradiated Nanocystalline Gold. . . . Chimi, Y.; Iwase, A.; Ishikawa, N.; Kobiyama, M.; Inami, T.; Okuda, S. . . . September 2001 . . . JAERI, Ibaraki, Japan; Ibaraki University, Ibaraki, Japan; Tsukuba Institute of Science and Technology, Ibaraki, Japan.

J. Nucl. Mater., 297, 358-360 . . . An Estimate of the High Temperature, Metal Rich Phase Boundary of Plutonium Sesquioxide. . . .Sheldon, R.I. . . . September 2001 . . . Los Alamos National Laboratory, Los Alamos, NM.

J. Nucl. Mater., 298, 1-10 . . . Role and Properties of the Gel Formed During Nuclear Glass Alteration: Importance of Gel Formation Conditions. . . . Gin, S.; Ribet, I.; Couillard, M. . . . September 2001 . . . Commissariat á l'Energie Atomique, Bagnols-sur-Cèze, France.

J. Nucl. Mater., 298, 11-18 . . . The Effect of Clay on the Dissolution of Nuclear Waste Glass. . . . Lemmens, K. . . . September 2001 . . . SCK-CEN, Mol, Belgium.

J. Nucl. Mater., 298, 19-26 . . . A Proposition for an Improved Theoretical Treatment of the Corrosion of Multi-Component Glasses. . . . Conradt, R. . . . September 2001 . . . Institut fur Gesteinshuttenkunde, Aachen, Germany.

J. Nucl. Mater., 298, 27-36 . . . Present Understanding of R7T7 Glass Alteration Kinetics and Their Impact on Long-Term Behavior Modeling. . . . Vernaz, E.; Gin, S. Jegou, C.; Ribet, I. . . . September 2001 . . . Commissariat á l'Energie Atomique, Bagnols-sur-Cèze, France.

J. Nucl. Mater., 298, 37-46 . . . New Techniques for Modelling Glass Dissolution. . . . Aertsens, M.; Ghaleb, D. . . . September 2001 . . . SCK-CEN, Mol, Belgium; DCC/DRRV/SCD/LEAM, Bagnols-sur-Cèze, France.

J. Nucl. Mater., 298, 47-54 . . . Overview of Actinides (Np, Pu, Am) and Tc Release from Waste Glasses: Influence of Solution Composition. . . . Pirlet, V. . . . September 2001 . . . SCK-CEN, Mol, Belgium.

J. Nucl. Mater., 298, 55-62 . . . Long-Term Alteration Mechanisms in Water for SON68 Radioactive Borosilicate Glass. . . . Advocat, T.; Jollivet, P.; Crovisier, J.L.; del Nero, M. . . . September 2001 . . . CEA/DIEC-Marcoule, Bagnols-sur-Cèze, France; CNRS/CGS, Strasbourg, France; In2P3-Ires, Strasbourg, France.

J. Nucl. Mater., 298, 63-68 . . . The Effect of Coprecipitation in Some Key Spent Fuel Elements. . . . Quiñones, J.; Serrano, J.; Diaz Arocas, P. . . . September 2001 . . . CIEMAT, Madrid, Spain.

J. Nucl. Mater., 298, 69-77 . . . Glass Dissolution: Testing and Modeling for Long-Term Behavior. . . . Strachan, D.M. . . . September 2001 . . . Pacific Northwest National Laboratory, Richland, WA.

J. Nucl. Mater., 298, 78-85 . . . US Field Testing Programs and Results. . . . Wicks, G.G. . . . September 2001 . . . Savannah River Technology Center, Aiken, SC.

J. Nucl. Mater., 298, 86-94 . . . In Situ Testing of the Chemical Durability of Vitrified High-Level Waste in a Boom Clay Formation in Belgium: Discussion of Recent Data and Concept of a New Test . . . Van Iseghem, P.; Valcke, E.; Lodding, A. . . . September 2001 . . . SCK-CEN, Mol, Belgium; Chalmers University of Technology, Gothenburg, Sweden.

J. Nucl. Mater., 298, 95-111 . . . Near-Field Performance Assessment for a Low-Activity Waste Glass Disposal System: Laboratory Testing to Modeling Results. . . . McGrail, B.P. et al. . . . September 2001 . . . Pacific Northwest National Laboratory, Richland, WA; CH2M Hill, Inc., Richland, WA; Fluor Federal Services, Richland, WA.

J. Nucl. Mater., 298, 112-124 . . . First-Order Dissolution Rate Law and the Role of Surface Layers in Glass Performance Assessment. . . . Grambow, B.; Müller, R. . . . September 2001 . . . SUBATECH, Nantes, France; Institut fur Nukleare Entsorgung, Karlsruhe, Germany.

J. Nucl. Mater., 298, 125-135 . . . Performance Assessment of the Disposal of Vitrified High-Level Waste in a Clay Layer. . . . Mallants, D.; Marivoet, J.; Sillen, X. . . . September 2001 . . . Belgian Nuclear Research Center, Mol, Belgium.

J. Nucl. Mater., 298, 136-144 . . . Database Development of Glass Dissolution and Radionuclide Migration for Performance Analysis of HLW Repository in Japan. . . . Yui, M. . . . September 2001 . . . JNC-Tokai Works, Ibaraki-ken, Japan.

J. Nucl. Mater., 298, 145-149 . . . Numerical Modelling of Glass Dissolution: Gel Layer Morphology. . . . Devreux, F.; Barboux, P. . . . September 2001 . . . Ecole Polytechnique & CNRS, Palaiseau, France.

J. Nucl. Mater., 298, 150-154 . . . Release of Boron and Cesium or Uranium from Simulated Borosilicate Waste Glasses Through a Compacted Ca-Bentonite Layer. . . . Chun, K.S.; Kim, S.S.; Kang, C.H. . . . September 2001 . . . Korea Atomic Energy Research Institute, Taejon, South Korea.

J. Nucl. Mater., 298, 155-162 . . . Determination of Sorption Isotherms for Eu, Th, U and Am on the Gel Layer of Corroded HLW Glass. . . . Luckscheiter, B.; Kienzler, B. . . . September 2001 . . . Institut für Nukleare Entsorgungstechnik, Karlsruhe, Germany.

J. Nucl. Mater., 298, 163-167 . . . Release and Retention of Uranium During Glass Corrosion. . . . Maeda, T. et al. . . . September 2001 . . . JAERI, Ibaraki, Japan; NGK Insulators, Japan; Kyushu University, Japan.

J. Nucl. Mater., 298, 168-173 . . . Leaching and Migration of Neptunium in a Simulated Engineered Barrier System Consisting of HLW Glass and Compacted Bentonite. . . . Inagaki, Y. et al. . . . September 2001 . . . Kyushu University, Fukuoka, Japan; JAERI, Ibaraki, Japan.

J. Nucl. Mater., 298, 174-179 . . . Waste Glass Behavior in a Loamy Soil of a Wet Repository Site. . . . Ojovan, M.I. et al. . . . September 2001 . . . Scientific and Industrial Association 'Radon', Moscow, Russia.

J. Nucl. Mater., 298, 180-183 . . . A Comparison of HLW-Glass and PWR-Borate Waste Glass. . . . Shanggeng Luo; Jiawei Sheng; Baolong Tang . . . September 2001 . . . China Institute of Atomic Energy, Beijing, People's Republic of China.

J. Nucl. Mater., 298, 184-191 . . . Effect of a Siliceous Additive on Aqueous Alteration of Waste Glass with Engineered Barrier Materials. . . . Mitsui, S.; Aoki, R. . . . September 2001 . . . Japan Nuclear Cycle Development Institute, Ibaraki, Japan; Nuclear Energy Systems Inc., Ibaraki, Japan.

J. Nucl. Mater., 298, 192-196 . . . Application of Electrochemical Impedance Spectroscopy (EIS) for In Situ Study of Glass Alteration. . . . Chaulet, D.; Martemianov, S.; Thomassin, J.H.; Le Coustumer, P. . . . September 2001 . . . Université de Poitiers, Poitiers, France.

J. Nucl. Mater., 298, 197-202 . . . In-Depth Distributions of Elements in Leached Layers on Two HLW Waste Glasses After Burial in Clay; Step-Scan by SIMS. . . . Lodding, A.; Van Iseghem, P. . . . September 2001 . . . Chalmers University of Technology, Gothenburg, Sweden; SCK-CEN, Mol, Belgium.

Nucl. Eng. Design, 208, 123-131 . . . Developing a Generalized Flaw Distribution for Reactor Pressure Vessels. . . . Jackson, D.A.; Doctor, S.R.; Schuster, G.; Simonen, F. . . . September 2001 . . . US Nuclear Regulatory Commission, Washington, DC; Pacific Northwest National Laboratory, Richland, WA.

Nucl. Eng. Design, 208, 143-165 . . . Evaluation of Environmental Effects on Fatigue Life of Piping. . . . Simonen, F.A. et al. . . . September 2001 . . . Pacific Northwest National Laboratory, Richland, WA; Engineering Mechanics Technology, San Jose, CA; US Nuclear Regulatory Commission, Washington, DC.

Nucl. Eng. Design, 208, 167-179 . . . Structural Analysis of Electrosleeved Tubes Under Severe Accident Transients. . . . Majumdar, S. . . . September 2001 . . . Argonne National Laboratory, Argonne, IL.

Nucl. Eng. Design, 208, 181-189 . . . Intercomparison of Results for a PRW Rod Ejection Accident. . . . Diamond, D.J. et al. . . . September 2001 . . . Brookhaven National Laboratory, Upton, NY; Kurchatov Institute, Moscow, Russia; Institute for Protection and Nuclear Safety, Cadarache, France; Atomic Energy Commission, Saclay, France.

Nucl. Eng. Design, 208, 191-203 . . . Fission Product Release Under Severe Accidental Conditions: General Presentation of the Program and Synthesis of VERCORS 1-6 Results. . . . Ducros, G.; Malgouyres, P.P.; Kissane, M.; Boulaud, D.; Durin, M. . . . September 2001 . . . Commissariat á l'Energie Atomique, Grenoble, France; Institut de Protection et de Surete Nucleaire, Saint Paul les Durance, Gif-sur-Yvette, and Fontenay aux Roses, France.

Nucl. Eng. Design, 208, 205-214 . . . Taking Burnup Credit into Account in Criticality Studies: The Situation as it is Now and the Prospect for the Future. . . . Cousinou, P. et al. . . . September 2001 . . . IPSN, Fontenay aux Roses, France; EDF, Villeurbanne, France; Framatome, Lyon Cedex, France; Commissariat a l'Energie Atomique, St. Paul lez Durance, France; COGEMA La Hague, Baumont Hague, France.

Prog. Nucl. Energy, 39, 119-144 . . . 3D Radiation Transport Benchmark Problems and Results for Simple Geometries with Void Region. . . . Kobayashi, K.; Sugimura, N. . . . 2001 . . . Kyoto University, Kyoto, Japan; JAERI, Ibaraki-ken, Japan.

Prog. Nucl. Energy, 39, 145-153 . . . Reference Solutions for 3-D Radiation Transport Benchmarks by a Monte Carlo Code GMVP. . . . Nagaya, Y. . . . 2001 . . . JAERI, Ibaraki-ken, Japan.

Prog. Nucl. Energy, 39, 155-166 . . . TORT Solutions for the 3D Radiation Transport Benchmarks for Simple Geometries with Void Region. . . . Azmy, Y.Y.; Gallmeier, F.X.; Lillie, D.A. . . . 2001 . . . Oak Ridge National Laboratory, Oak Ridge, TN.

Prog. Nucl. Energy, 39, 167-179 . . . TORT Solutions with FNSUNCL3 for Kobayashi's 3D Benchmarks. . . . Konno, C. . . . 2001 . . . JAERI, Ibaraki-ken, Japan.

Prog. Nucl. Energy, 39, 181-190 . . . PARTISN Calculations of 3D Radiation Transport Benchmarks for Simple Geometries with Void Regions. . . . Alcouffe, R.E. . . . 2001 . . . Los Alamos National Laboratory, Los Alamos, NM.

Prog. Nucl. Energy, 39, 191-206 . . . Effectiveness of PENTRAN™'s Unique Numerics for Simulation of the Kobayashi Benchmarks. . . . Haghighat, A.; Sjoden, G.E.; Kucukboyaci, V.N. . . . 2001 . . . Penn State University, University Park, PA.

Prog. Nucl. Energy, 39, 207-221 . . . Deterministic Solutions for 3D Kobayashi Benchmarks. . . . Zmijarevic, I.; Sanchez, R. . . . 2001 . . . CEA Saclay, Gif-sur-Yvette, France.

Prog. Nucl. Energy, 39, 223-242 . . . Improvements in the Long Characteristics Method and Their Efficiency for Deep Penetration Calculations. . . . Suslov, I. . . . 2001 . . . DMT/SERMA, Gif-sur-Yvette, France.

Prog. Nucl. Energy, 39, 243-261 . . . Finite Element-Spherical Harmonics Solutions of the 3D Kobayashi Benchmarks with Ray-Tracing Void Treatment. . . . De Oliveira, C.R.E.; Eaton, M.D.; Umpleby, A.P.; Pain, C.C. . . . 2001 . . . Imperial College of Science, Technology and Medicine, London, UK.

Prog. Nucl. Energy, 39, 263-284 . . . Spherical Harmonic Solutions of the Boltzmann Transport Equation Via Discrete Ordinates. . . . Brown, P.N.; Chang, B.; Hanebutte, U.R. . . . 2001 . . . Lawrence Livermore National Laboratory, Livermore, CA.

Nucl. Sci. Eng., 139, 1-23 . . . Development of Methods for Calculation of Deuteron-Lithium and Neutron-Lithium Cross Sections for Energies up to 50 MeV. . . . Konobeyev, A.Yu.; Korovin, Yu.A.; Pereslavtsev, P.E. . . . September 2001 . . . Obninsk Institute of Nuclear Power Engineering, Obninsk, Russia; Association FZK-Euratom, Karlsruhe, Germany.

Nucl. Sci. Eng., 139, 24-32 . . . Threshold Reaction Cross Sections of Nickel Isotopes, Averaged Over a ²³⁵U Fission Neutron Spectrum. . . . Arribére, M.A.; Guevara, S.R.; Suárez, P.M.; Kestelman, A.J. . . . September 2001 . . . Comisión Nacional de Energía Atómica, Bariloche, Argentina.

Nucl. Sci. Eng., 139, 33-46 . . . Nonnegative Anisotropic Group Cross Sections: A Hybrid Monte Carlo-Discrete Elements-Discrete Ordinates Approach. . . . DelGrande, J.M.; Mathews, K.A. . . . September 2001 . . . Air Force Institute of Technology, Wright-Patterson AFB, OH.

Nucl. Sci. Eng., 139, 47-65 . . . A Transport Condensed History Algorithm for Electron Monte Carlo Simulations. . . . Tolar, D.R., Jr.; Larsen, E.W. . . . September 2001 . . . Lawrence Livermore National Laboratory, Livermore, CA; University of Michigan, Ann Arbor, MI.

Nucl. Sci. Eng., 139, 66-77 . . . Neutron Transport in Spatially Random Media: Eigenvalue Problems. . . . Williams, M.M.R.; Larsen, E.W. . . . September 2001 . . . University of Michigan, Ann Arbor, MI.

Nucl. Sci. Eng., 139, 78-95 . . . A Spatial Kinetics Method Ensuring Neutronic Balance with Thermical-Hydraulic Feedback and Its Application to a Main Steam Line Break. . . . Asahi, Y.; Okumura, K.; Ose, Y. . . . September 2001 . . . JAERI, Ibaraki-ken, Japan; Katena Company, Tokyo, Japan.

Nucl. Sci. Eng., 139, 96-104 . . . Genetic Algorithms for Estimating Effective Parameters in a Lumped Reactor Model for Reactivity Predictions. . . . Marseguerra, M.; Zio, E. . . . September 2001 . . . Polytechnic of Milan, Milano, Italy.

Nucl. Sci. Eng., 139, 105-110 . . . An Alternate Formulation of the Nodal Expansion Method. . . . Keqiang Ruan, Xiaogang Xue, Xuedong Fu . . . September 2001 . . . China Institute of Atomic Energy, Beijing, China.

Ann. Nucl. Energy, 28, 1583-1594 . . . Simulation of a Small Loss of Coolant Accident by Using RETINA V1.0D Code. . . . Házi, G.; Mayer, G.; Farkas, I.; Makovi, P.; El-Kafas, A.A. . . . November 2001 . . . KFKI Atomic Energy Research Institute, Budapest, Hungary; Atomic Energy Authority, Cairo, Egypt.

Ann. Nucl. Energy, 28, 1595-1611 . . . Calculating Reactor Transfer Functions by Padé Approximation via Lanczos Algorithm. . . . Kuang, Z.; Pazsit, I.; Ruhe, A. . . . November 2001 . . . Chalmers University of Technology, Göteborg, Sweden.

Ann. Nucl. Energy, 28, 1613-1624 . . . Control of Reactor Pulses by External Neutron Injection. . . . Pepyolyshev, Yu.N.; Popov, A.K. . . . November 2001 . . . Joint Institute for Nuclear Research, Moscow, Russia.

Ann. Nucl. Energy, 28, 1625-1641 . . . Relationship Between Flux Tilt in Two-Energy-Group and Eigenvalue Separation. . . . Pyeon, C.H.; Misawa, T.; Shiroya, S.; Yamane, Y. . . . November 2001 . . . Kyoto University, Kyoto, Japan; Nagoya University, Nagoya, Japan.

Ann. Nucl. Energy, 28, 1643-1652 . . . Prompt Fission Neutron Spectrum Calculations for n+²³⁸U Reaction Using the Multi-Modal Model. . . . Vladuca, G.; Tudora, A. . . . November 2001 . . . Bucharest University, Bucharest-Magurele, Romania.

Ann. Nucl. Energy, 28, 1653-1665 . . . Prompt Fission Neutron Multiplicity and Spectrum Evaluations for n+²³⁸U Reaction. . . . Vladuca, G.; Tudora, A. . . . November 2001 . . . Bucharest University, Bucharest-Magurele, Romania.

Ann. Nucl. Energy, 28, 1667-1682 . . . AXIAL: A System for Boiling Water Reactor Fuel Assembly Axial Optimization Using Genetic Algorithms. . . . Martín del Campo, C.; François, J.L.; López, H.A. . . . November 2001 . . . Universidad Nacional Autónoma de México, Morelos, Mexico.

Ann. Nucl. Energy, 28, 1683-1695 . . . An Experimental Study and Assessment of Existing Friction Factor Correlations for Wire-Wrapped Fuel Assemblies. . . . Chun, M-H.; Seo, K-W. . . . November 2001 . . . Korea Advanced Institute of Science and Technology, Yusongj-gu, South Korea.

Ann. Nucl. Energy, 28, 1697-1716 . . . The Effect of Stochastic Perturbation of Fuel Distribution on the Criticality of a One Speed Reactor and the Development of Multi-Material Multinomial Line Statistics . . . Jahshan, S.N.;Singleterry, R.C. . . . November 2001 . . . NASA Langley Research Center, Hampton, VA.

Ann. Nucl. Energy, 28, 1717-1732 . . . Safety Characteristics of the Multipurpose Fast Reactor (MPFR). . . . Netchaev, A.; Hizume, Y.; Endo, H.; Sawada, T.; Ninokata, H. . . . November 2001 . . . Tokyo Institute of Technology, Tokyo, Japan; Toshiba Corp., Yokohama, Japan.

Ann. Nucl. Energy, 28, 1733-1744 . . . A Comparative Study to Investigate Burnup in Research Reactor Fuel Using Two Independent Experimental Methods. . . . Iqbal, M.; Mehmood, T.; Ayazuddin, S.K.; Salahuddin, A.; Pervez, S. . . .November 2001 . . . Pakistan Institute of Nuclear Science and Technology, Islamabad, Pakistan.

Ann. Nucl. Energy, 28, 1745-1758 . . . Fast-Neutrons Incident on Holmium. . . . Smith, A.B. . . . November 2001 . . . Argonne National Laboratory, Argonne, IL.

Ann. Nucl. Energy, 28, 1759-1772 . . . Point Kinetic Model for Fluid Fuel Systems. . . . Lapenta, G.; Mattioda, F.; Ravetto, P. . . . November 2001 . . . Politecnico di Torino, Torino, Italy.

Ann. Nucl. Energy, 28, 1773-1782 . . . Calculation of the Moderator Temperature Coefficient of Reactivity for Water Moderated Reactors. . . . Mourtzanos, K.; Housiadas, C.; Antonopoulos-Domis, M. . . . November 2001 . . . "Demokritos" National Centre for Scientific Research, Athens, Greece.

Fus. Eng. Design, 55, 359-364 . . . Mean Residence Time Method of Tritium Inventory Calculation. . . . Deng Baiquan, Huang Jinhua . . . September 2001 . . . Southwestern Institute of Physics, Sichuan, China.

Fus. Eng. Design, 55, 365-372 . . . Analysis of the Karlsruhe Neutron Transmission Experiment Using MCNP with Various Beryllium Nuclear Data. . . . Tayama, R. et al. . . . September 2001 . . . Hitachi Engineering Co., Ltd.; Ibaraki-ken, Japan; Forschungszentrum Karlsruhe, Karlsruhe, Germany.

Fus. Eng. Design, 55, 373-385 . . . Set of Benchmark Experiments on Slit Shielding Compositions of Thermonuclear Reactors . . . Andreev, M.I. et al. . . . September 2001 . . . Moscow State Engineering Physics Institute, Moscow, Russia; Russian Research Institute of Technical Physics, Chelyabinsk Region, Russia; State Research Center of Russian Federation, Kaluga Region, Russia; Research, Development and Design Institute of Nuclear Power Engineering, Moscow, Russia.

Fus. Eng. Design, 55, 387-396 . . . Issues in Capsule Fabrication and Injection into a Wet-Walled IFE Reactor. . . . Norimatsu, T.; Nagai, K.; Takaki, I.; Yamanaka, T. . . . September 2001 . . . Osaka University, Osaka, Japan.

Fus. Eng. Design, 55, 397-410 . . . Manufacturing and Maintenance Technologies Developed for a Thick-Wall Structure of the ITER Vacuum Vessel . . . Onozuka, M. et al. . . . September 2001 . . . ITER Garching JWS, Garching, Germany; CEA, Arcueil, France; GAER Systems, Marseille, France; Echoplus, Moscow, Russia; EDFA, Garching, Germany; JAERI, Tokai, Japan; Efremov Institute, St. Petersburg, Russia; Boeing North American, Inc., Canoga Park, CA; Oak Ridge National Laboratory, Oak Ridge, TN; TWI, Cambridge, UK; CEA, Saclay, France; University of Hannover, Hannover, Germany.

Fus. Eng. Design, 55, 411-418 . . . Proposal of Shutdown Dose Estimation Method by Monte Carlo Code. . . . Valenza, D.; Iida, H.; Plenteda, R.; Santoro, R.T. . . . September 2001 . . . Max Planck Institut fur Plasmaphysik, Garching bei München, Germany; ITER Joint Central Team, Garching bei München, Germany; CTBTO, Vienna, Austria; Oak Ridge National Laboratory, Oak Ridge, TN.

Fus. Eng. Design, 55, 419-436 . . . Dielectric Window for Reactor Like ICRF Vacuum Transmission Line. . . . Heikinheimo, L. et al. . . . September 2001 . . . VTT Manufacturing, VTT, Finland; VTT Chemical Technology, VTT, Finland; Fortum Power and Heat Oy, Fortum, Finland; JET Joint Undertaking, Oxon, UK; Helsinki University of Technology, HUT, Finland; VTT Energy, VTT, Finland.

Fus. Eng. Design, 55, 437-447 . . . The Removal of Co-Deposited Carbon/Deuterium Films from Stainless Steel and Tungsten by Transferred-Arc Cleaning. . . . Hollis, K.J.; Castro, R.G.; Doerner, R.P.; Maggiore, C.J. . . . September 2001 . . . Los Alamos National Laboratory, Los Alamos, NM; University of California, San Diego, La Jolla, CA.

Fus. Eng. Design, 55, 449-455 . . . Tritium Contamination and Decontamination Study on Materials for ITER Remote Handling Equipment. . . . Oya, Y. et al. . . . September 2001 . . . JAERI, Ibaraki-ken, Japan.

Fus. Eng. Design, 55, 457-465 . . . An Analysis of Variable Magnetic Damping of a Cantilever Beam-Plate with End Coils in Transverse Magnetic Fields. . . . Xiao Jing Zheng; Zhou, Y-H.; Miya, K. . . . September 2001 . . . Lanzhou University, Gansu, China; University of Tokyo, Tokyo, Japan.

Fus. Eng. Design, 55, 467-475 . . . Velocity Distribution Functions and Reactivity of D-T Fusion Plasma with Spin-Polarized Fuel. . . . Takahashi, T.; Nakao, Y. . . . September 2001 . . . Gunma University, Gunma, Japan; Kyushu University, Fukuoka, Japan.

Fus. Eng. Design, 55, 477-500 . . . Comparative Studies of the dW/dt Effect in the Net Heating Power for Ignition Analyses. . . . Mitarai, W.; Honda, T.; Nishitani, T.; Muraoka, K. . . . September 2001 . . . Kyushu Tokai University, Kumamoto, Japan; Hitachi Ltd., Ibaraki, Japan; JAERI, Ibaraki, Japan.

Fus. Eng. Design, 55, 501-512 . . . Re-Investigations of Integral Neutron Multiplication Experiments with 14 MeV Neutrons in Lead. . . . Sharma, A.R.; Chandra, D.; Chaturvedi, S.; Ganesan, S.; Wienke, H. . . . September 2001 . . . Institute for Plasma Research, Gujrat, India; Bhabha Atomic Research Centre, Mumbai, India; SCK-CEN, Belgian Nuclear Research Center, Mol, Belgium.

Fus. Eng. Design, 55, 513-520 . . . Implantation Driven Permeation Behavior of Deuterium Through Pure Tungsten. . . . Nakamura, H.; Hayashi, T.; Nishi, M.; Arita, M.; Okuno, K. . . . September 2001 . . . JAERI, Ibaraki, Japan.

Fus. Eng. Design, 55, 521-534 . . . Design and Thermal-Hydraulic Analysis of PFC Baking for SST-1 Tokamak. . . . Chaudhuri, P.; Reddy, D.C.; Khirwadkar, S.; Prakash, N.R.; Santra, P.; Saxena, Y.C. . . . September 2001 . . . Institute for Plasma Research Bhat, Gandhinagar, India.

Fus. Eng. Design, 55, 535-540 . . . Perspective on Fusion Research in China (2) Fusion Activities in China with Special Intonation on Hybrid Reactor Program. . . . Qiu Lijian . . .September 2001 . . . Chinese Academia of Sciences, Anhui, China.

KEK Proceedings 2000-14, 1-11 . . . Critical Electric Field in a Multi-Wire Chamber. . . . Ohama, T.; Ishihara, N.; Okuma, H.; Konno, K. . . . August 2000 . . . High Energy Accelerator Research Organization (KEK), Ibaraki, Japan; REPIC Corp., Tokyo, Japan.

KEK Proceedings 2000-14, 12-21 . . . Helium-Filled Proportional Counter (~4.2K) and Its New Application . . .Masaoka, S.; Katano, R.; Isozumi, Y. . . . August 2000 . . . Kyoto University, Kyoto, Japan.

KEK Proceedings 2000-14, 21-31 . . . Positron-Sensitive Proportional Counter with Resistive Anode. . . . Ohsawa, D.; Masaoka, S.; Katano, R. . . . August 2000 . . . National Institute of Radiological Sciences, Chiba, Japan; Kyoto University, Kyoto, Japan.

KEK Proceedings 2000-14, 55-63 . . . Absolute Scintillation Efficiency of NaI(Tl) Crystals. . . . Shibamura, E.; Sasaki, S.; Tawara, H.; Saito, K.; Miyajima, M. . . . August 2000 . . . Saitama Prefectual University, Saitama, Japan; High Energy Accelerator Research Organization, Ibaraki, Japan; Graduate University for Advanced Studies, Ibaraki, Japan; Fukui University, Fukui, Japan.

KEK Proceedings 2000-14, 102-110 . . . Development of Fast Neutron Profile Method. . . . Miura, T. et al. . . . August 2000 . . . Tohoku University, Sendai, Japan.

KEK Proceedings 2000-14, 123-131 . . . Calculation of Neutron Detection Efficiencies for NE-213 Scintillator Up to 1 GeV. . . . Daiki, S.; Hirohiko, K.; Nobuhiro, S.; Kenji, I. . . . August 2000 . . . Kyushu University, Fukuoka, Japan.

KEK Proceedings 2000-14, 142-150 . . . Development of Gamma Ray Monitoring Using CdZnTe Semiconductor Detector. . . . Rasolonjatovo, A.H.D. et al. . . . August 2000 . . . Tohoku University, Tohoku, Japan; Mitsubishi Electric Corp., Japan.

KEK Proceedings 2000-14, 155-162 . . . Neutron/Proton Discrimination Characteristics of Spaceborne Neutron Monitors . . . Makihara, Y. et al. . . . August 2000 . . . Nagoya University, Nagoya, Japan; Electrotechnical Laboratory, Tsukuba, Japan; Institute of Physical and Chemical Research, Wako, Japan; Mitsubishi Research Institute Inc., Tokyo, Japan; Nuclear Development Co., Omiya, Japan; Aichi Institute of Technology, Toyota, Japan.

KEK Proceedings 2000-14, 191-200 . . . A Measurement of Number of Scintillation Photons in Rare Gases. . . . Saito, K.; Sasaki, S.; Tawara, H.; Shibamura, E. . . . August 2000 . . . Graduate University for Advanced Studies, Ibaraki, Japan; High Energy Accelerator Research Organization, Ibaraki, Japan; Saitama Prefectual University, Saitama, Japan.

KEK Proceedings 2000-14, 211-217 . . . Monte Carlo Calculation of Detection Efficiency of Coaxial GE Detector. . . . Kugii, H. et al. . . . August 2000 . . . University of Tokushima, Tokushima, Japan; University Putra Malaysia, Selangor, Malaysia.

KEK Proceedings 2000-14, 226-235 . . . Development of a Portable Radon Progeny Monitor. . . . Iimoto, T.; Kosako, T.; Sugiura, N. . . . August 2000 . . . University of Tokyo, Tokyo, Japan.

KEK Proceedings 2000-14, 253-259 . . . Development of a Compact Gas Counter for Neutron Elastic Recoil Detection Analysis. . . . Mizota, T.; Nakao, S.; Niwa, H.; Saitoh, K. . . . August 2000 . . . National Industrial Research Institute of Nagoya, Nagoya, Japan.