Radiation Safety Information Computational Center
	Oak Ridge National Laboratory Post Office Box 2008  Oak Ridge, Tennessee 37831-6362  Managed by  UT-Battelle, LLC  for the U.S. Department of Energy  under contract DE-AC05-00OR22725  Phone No. 865-574-6176  FAX 865-574-6182  Internet: PDC@ORNL.GOV  WWW: http://www-rsicc.ornl.gov/rsic.html
No. 427	September 2000
"My grandfather once told me that there are two kinds of people: Those who do the work and those who take the credit. He told me to try to be in the first group; there was much less competition." -- Indira Gandhi, the late Prime Minister of India

• Thanks for Responding
• More on the Los Alamos Fire
• NRC Codes Made Available
• CHANGES TO THE COMPUTER SOFTWARE COLLECTION
• CONFERENCES, COURSES, SYMPOSIA
• SCALE Training Course Schedule for 2000
• Practical MCNP for the Health /Medical Physicist & Rad Engineer
• MCNP and Visual Editor Training Course
• MCNP™ Workshops for the Year 2000
• Calendar
• AUGUST ACCESSION OF LITERATURE
• Radiation Shielding Literature

Our home in Los Alamos survived the Cerro Grande fire. Since I am semi-retired and do not require residency in Los Alamos, we have leased our home to a young couple with two children who lost everything. We are living in a small apartment in Albuquerque until their home is rebuilt.

The note from the MCNP Team on the Los Alamos Fire [July issue] didn't do justice to the fire and its aftermath. Things will never be the same in my lifetime - even the lifetimes of my grandchildren. The results of the fire are both physical and emotional. The generosity of those not affected was astounding - there was almost a compulsion to give. Many of those directly affected find it difficult to be gracious recipients. It would take an encyclopedia to document the experiences of the 20,000 evacuees. My daughter spent four 16 hour days assisting with the preparation of 6,000 meals/day for the firefighters, and my wife spent a week of 12 hour days distributing clothing that had been donated from all over the world. Our most telling experience was the young girl who was brought to the clothing distribution center after viewing her burnt out home for the first time - she was in shock and refused anything until she found a teddy bear just like the one that had been lost!

CCC-364/SANDOR (Sandia ORIGEN) 
PSR-464/SOLA-LOOP
DLC-125/FIREDATA
 

CCC-705/MCNPX(TM) Version 2.1.5
OP SYS: Unix
Language: Fortran 77, C
Computers: Workstations, PC
Format: tar

Accelerator Production of Tritium Technical Project Office, Los Alamos National Laboratory, Los Alamos, New Mexico, contributed this Monte Carlo N-Particle transport code system for multiparticle and high energy applications. MCNPX extends the CCC-660/MCNP4B code to all particles and all energies. Neutron tabular data are used as in MCNP4B; above the table energy limits, physics modules are used. Current physics modules include the Bertini and ISABEL models taken from the LAHET Code System (LCS) and CEM. An old version of FLUKA is available for calculations above the range of INC physics applicability. MCNPX eliminates the need now present in LCS to transfer large files between separate codes. MCNPX is released with the LA150N library, which is included in the DLC-205/MCNPXDATA package; and further 150 MeV libraries will follow shortly for protons and photonuclear interactions. In addition, variance reduction schemes (such as secondary particle biasing) and new tallies have been created specific to the intermediate and high energy physics ranges. The 'mesh' and 'radiography' tallies have been included for 2- and 3-dimensional imaging purposes. Energy deposition has received a substantial reworking based on the demands of charged-particle high-energy physics. An auxilliary program, GRIDCONV, converts the mesh and radiography tally results for viewing by independent graphics packages. GRIDCONV will soon be extended to convert any tally available in a mctal file.

MCNPX executes on many computers running Unix operating systems. C and Fortran-77 compilers and the GNU make utility are required for installation. RSICC tested this release on the following systems:

• AIX 4.3.3 (IBM 43P-260) with XL C/C++ 4.4; XL Fortran 6.1
• Redhat Linux Version 6.1 on 450 MHz Pentium III (9 nodes) with g77
• Sun Solaris 2.6 on UltraSparc 60 using F77 Version 5.0 and C/C++ Version 5.0
• HP B1000 (PA-8500) under HP-UX 10.20 with FORTRAN 77 V0.20 and HP C V10.32.00 (compiled with no optimization)
• DEC 500 AU under Digital Unix 4.0D with DEC Fortran 5.1-8 and DEC C 5.6-075
• SGI MIPS R10000 (225MHz) under IRIX 6.5.5 with MIPS Fortran 77 Version 7.3

PSR-496/SAFE-D, SAFE-R
OP SYS: Windows
Language: Fortran 77
Computers: PC, RS/6000, Unix
Format: DOS

Kansas State University, Manhattan, Kansas, contributed SAFE-D and SAFE-R, which are two separate but similar FORTRAN computer codes for the analysis of component failure data with a compound statistical model. The SAFE-D code (Statistical Analysis for Failure Estimation-failure-on-Demand) analyzes data which give the observed number of failures (failure to respond properly) in a specified number of demands for several similar components that should change their condition upon demand. The second program, SAFE-R (Statistical Analysis for Failure Estimation-failure Rate) is to be used to analyze normally operating components for which the observed number of failures in a specified operating time is given. In both these codes the failure parameter (failure probability per demand for SAFE-D or failure rate for SAFE-R) may be assumed equal for all similar components (the homogeneous failure model) or may be assumed to be a random variable distributed among similar components according to a prior distribution (the heterogeneous or compound failure model).

SAFE-D and SAFE-R can be run on personal computers, IBM RS/6000 or DEC Alpha Unix workstations. Either a Fortran 77 or 90 compiler is required on the DEC and IBM RS/6000 Unix workstations. The executables in the package were created with the Lahey LF90 Fortran Compiler Version 2.0li under Windows95. The package is transmitted on two 3.5-in. diskettes written as self-extracting compressed DOS files which include source code, sample problems, and PC executables. Reference: NUREG/CR-2375 KSU-2075d (December 1997). Fortran 77 and 90; IBM PC, IBM RS/6000, DEC Alpha (P00496/MNYCP/00).
 

DLC-205/MCNPXDATA
OP SYS: Unix
Computers: Workstations, PC
Format: tar

Los Alamos National Laboratory, Los Alamos, New Mexico, contributed this package of standard neutron, photon, and electron data libraries for use with MCNPX. DLC-205/MCNPXDATA is for use with MCNPX and can be used with Versions 4B, 4C and later of the MCNP transport code. This data library provides a comprehensive set of cross sections for a wide range of radiation transport applications using the MCNPX Monte Carlo code package.

The DLC-205/MCNPXDATA package is comprised of DLC-200/MCNPDATA, which was released for use with MCNP4C, plus the LA150N library of 42 high energy neutron data tables, minus the EL03 library because the EL03 library is incompatible with MCNP4B, upon which MCNPX is currently based. In LA150N, the neutron energy is extended to 150 MeV except for Be-9, which only goes to 100 MeV. This library typically extends ENDF/B-VI data from 20 MeV to 150 MeV; therefore, charged particle and recoil nuclei data will sometimes not be available below 20 MeV. Exceptions are noted in the MCNPX User's Manual. All standard neutron libraries used with MCNP4B (originally distributed in DLC-189 and now included in DLC-205) can be used with MCNPX 2.1.5; however, they will not contain emission data for charged particles or recoil nuclei; therefore, these products will not be tracked upon production. The new neutron libraries developed for use with MCNP4C will work with MCNPX; however, some features specific to MCNP4C will not function. In particular, features related to probability tables and delayed neutrons will be ignored. Electron tables with zaid numbers ending in .01e will work, others will not. No data for charged particle projectiles will be available in DLC-205.

All data libraries are distributed in compressed mode. Files in the Unix tar file are in ASCII format and can be used with MCNPX on all computer platforms supported by the code. The files are distributed on CD in a GNU compressed tar file.

References: The following documents are distributed in electronic (PDF) form with the package: Revised Table G.2 for Appendix G of the MCNP4C manual, README (August 2000), LA-12891 (1994), X-6:HGH-93-77 (revised 1996), XTM:95-259 and LA-UR-96- 24 (1995), X-6:RCL-87-225 (1987), XCI-RN(U)98-041, LA-UR-98-5718, (December 1998), XTM:96-153 (April 1996), and XCI:CJW-99-25 (April 1999). (D00205/ALLCP/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.
 

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. For more information, http://www.cped.ornl.gov/scale/trcourse.html.
 

SCALE Shielding and Source Terms Course (October 16-20, 2000)

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 V.a Criticality Course (October 23-27, 2000)

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. KENO V.a is a fast, easy-to-use code that allows users to build complex geometry models using basic geometrical bodies of cuboids, spheres, cylinders, hemispheres, and hemicylinders. Two-dimensional color plots of the geometry model can be generated.
 

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 MCNP™ to solve a variety of practical problems in radiation shielding and dosimetry. The intent is to "jump start" the student toward using MCNP™ productively. Extensive interactive practice sessions are conducted on a personal computer. Topics will include overview of the MCNP™ 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 MCNP™ 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. 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; however, to guarantee a space payment must be received prior to the registration deadline. Please 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 the address above. The course is offered by Group ESH-4, Health Physics Measurements, Mail Stop G761, Los Alamos National Laboratory, Los Alamos, NM 87545 USA.

Inquiries regarding registration and class space availability should be made to David Seagraves, 505-667-4959, fax: 505-665-6071, e-mail: dseagraves@lanl.gov. Technical questions may also be directed to Dick Olsher, 505-667-3364, e-mail: dick@lanl.gov.
 

The source code package can be obtained directly from RSICC.

The class will combine teaching on MCNP physics, along with instructions on how to use the visual editor. Computer demonstrations and exercises will focus on creating and interrogating input files with the visual editor. Demonstrations of advanced visualization work using MCNP will also be made. The class will be taught on Pentium computers running the Linux operating system. Attendees are encouraged to bring their own input files for viewing and modifying in the visual editor. It is recommended that you have experience with MCNP before taking this class. For additional information contact Randy Schwarz, MS K8-34, P. O. Box 999, Richland, WA 99352 (509-372-4042, fax 509-372-6421, email randy.schwarz@pnl.gov, url http://www.pnl.gov/eshs/software/ved.html).
 
 

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.

Year 2000 classes will showcase the latest release of MCNP, Version 4C. Major new features that will be discussed include:

• Macrobodies
• Superimposed Importance Meshes
• ENDF/B-VI Improvements
• Perturbation Enhancements
• PC Enhancements
• Parallel Enhancements
• Alpha Eigenvalue Search
• Unresolved Resonance Range Probability Tables
• Cumulative Tallies
• Electron Physics Enhancements

October 2000

Safewaste International Conference 2000, Oct. 2-4, 2000, Montpellier Corum, France, sponsored by OECD/NEA and cosponsored by ANS. Contact: SFEN, 67, rue Blomet 75015, Paris, France (tel + 33 1 53 59 32 16, email aujay.sfen@wanadoo.fr).

6th Annual Workshop on Monte Carlo Simulation of Radiotherapy Treatment Sources Using the OMEGA/BEAM Code System, Oct. 2-5, 2000, Ottawa, Canada. Contact: Blake Walters, Ionizing Radiation Standards, National Research Council of Canada, Ottawa, Canada, K1A 0R6. (tel 613-993-2715, fax 613-952-9865, email bwalters@irs.phy.nrc.ca, url www.irs.inms.nrc.ca/inms/irs/BEAM/beamhome. html).

International Symposium on the Uranium Production Cycle and the Environment, Oct. 2-6, 2000, Vienna, Austria, sponsored by the International Atomic Energy Agency and others. Contact: R. Perricos, Conference Service Section, IAEA, P.O. Box 100, Wagramerstrasse 5, A-1400, Vienna, Austria (tel + 43 1 2600 21315, email official.mail@iaea.org, url www.iaea.org).

18th International IAEA Fusion Energy Conference, Oct. 4-10, 2000, Sorrento, Italy, sponsored by the International Atomic Energy Agency. Contact: IAEA, P.O. Box 100, Vienna International Centre, A-1400, Vienna, Austria (tel + 43 1 2600 21275, fax + 43 1 2600 29610, email official.mail@iaea.org, url www.iaea.org).

2000 TLG Decommissioning Conference, Oct. 8-14, 2000, Captiva Island, FL, sponsored by TLG Services, Inc. Contact TLG Services (tel 860-355-2300, fax 860-355-2705, url www.tlgservices.com/confrenc/confindx. htm).

Plutonium Management and Sustainable Development (Pu-2000), Oct. 9-11, 2000, Brussels, Belgium, sponsored by the Belgian Nuclear Society and others, and cosponsored by ANS. Contact: Werner Couwenbergh, BNS, Ravenstein St., 3-B 1000 Brussels, Belgium (tel +32 2 774 05 38, fax + 32 2 774 05 02, email pu2000@belgonucleaire.be , url www.sckcen.be/bns).

MCNP and Visual Editor Training Course, Oct. 9-12, 2000, Richland, Washington. Contact: Randy Schwarz, MS K8-34, P. O. Box 999, Richland, WA 99352 (509-372-4042, fax 509- 372-6421, email randy.schwarz@pnl.gov, url http://www.pnl.gov/eshs/software/ved.html).

2000 American Nuclear Society 14th Topical Meeting on the Technology of Fusion Energy, Oct. 15-19, 2000, Park City, Utah. Contact: url http://www.ambinet.com/ans/rps2000.htm.

International Symposium on Nuclear Techniques in Integrated Plant Nutrient, Water and Soil Management, Oct. 16-20, 2000, Vienna, Austria, sponsored by the International Atomic Energy Agency. Contact: IAEA, P.O. Box 100, Wagramerstrasse 5, A-1400 Vienna, Austria (tel + 43 1 26000, fax + 43 1 26007, email official.mail@iaea.org).

2000 Symposium on Nuclear Power Systems, Oct. 18-19, 2000, Lyon, France (held in conjunction with the Nuclear Science Symposium), sponsored by the Institute of Electrical and Electronic Engineeers. Contact: Jay Forster, GE Nuclear Energy (tel 408-925-5090, fax 408-925-5312, email jay.forster@gene.ge.com).

Communicating Nuclear Issues, Oct. 22-25, 2000, Cleveland, Ohio, sponsored by the Nuclear Energy Institute. Contact: NEI (tel 202-739-8000, fax 202-785-4019).

Eighth International Conference on Water Chemistry of Nuclear Reactor Systems, Oct. 22-26, 2000, Bournemouth, England, sponsored by the British Nuclear Energy Society. Contact: Andrew Tillbrook, BNES Secretary, 1 Great George St., London, SW1P 3AA, England (tel +020 7665 2241, fax +020 7799 1325, email tillbrook_a@ice.org.uk, url www.bnes.com).

4th International Workshop on Dosimetry for Radiation Processing, Oct. 22-27, 2000, San Diego, California. Contact: Dr. Harry Farrar IV, ASTM Committee E-10, 18 Flintlock Lane, Bell Canyon, CA 91307-1127 (tel 818-340-1227, fax 818-340-2132, email hfarrar4@aol.com).

International Conference on Advanced Monte Carlo for Radiation Physics, Particle Transport Simulation and Applications (MC2000), Oct. 23-26, 2000, Lisbon, Portugal. Contact: Instituto Tecnológico e Nuclear, MC2000 Conference Secretariat, Estrada Nacional 10, P-2686-953 Sacavem, Portugal (tel + 351-21-994 60 00 ext. 6154, fax + 351-21-994 10 39, email mc2000@itn1.itn.pt, or Dr. Pedro Vaz, Technical and Scientific Program Co-ordinator at email vaz@nea.fr, url http://lipulsi.lip.pt/mc2000/).

28th Water Reactor Safety Information Meeting, Oct. 23-25, 2000, Bethesda, MD, sponsored by Office of Nuclear Regulatory Research of the U.S. Nuclear Regulatory Commission. Contact: Susan Monteleone (tel 631-344-7235, fax 631-344-3957, email susanm2@bnl.gov, url www.wrsm.bnl.gov).

International Conference on Human Factors and Nuclear Safety, Oct. 23-26, 2000, Moscow, Russia, sponsored by the Nuclear Human Resource Professionals. Contact: Rick Habegger, NHRP (tel 919-367-9040, fax 919-367-0600, email rick@hrs-s.com).

Annual Conference of the Bulgarian Nuclear Society, Oct. 25-27, 2000, Sofia, Bulgaria. Contact: Vesselin Bliznakov, BNS, 132, Blvd. Kl. Ohridski, 1756 Sofia, Bulgaria (fax + 359 2 621059), or Lilia Stoeva (tel + 359 2 56 29 69, email lstoeva@solo.bg).

12th Pacific Basin Nuclear Conference, Oct. 29-Nov. 2, 2000, Seoul, Korea, sponsored by the Korea Atomic Industrial Forum, Inc. and the Korean Nuclear Society. Contact: PBNC 2000 Exhibition Secretariat, KAIF, Youido, P.O. Box 1021, Seoul 150-610, Korea (tel +82 2 785 2570, fax + 822 785 3975, url www.pbnc2000.com).

Ninth Annual Meeting of the Council on Ionizing Radiation Measurements and Standards, Oct. 30-Nov. 1, 2000, Gaithersburg, MD, cosponsored by the National Institute of Standards and Technology and the Council on Ionizing Radiation Measurements and Standards. Contact: Bert Coursey, NIST (tel 301-975-5584, fax 301-869-2279, email bert.coursey@nist.gov, web www.cirms.org).
 

November 2000

5th Radiation Physics Conference--Atomic Energy, Radiation Protection, Challenges and Strategies, Nov. 5-9, 2000, Cairo, Egypt. Contact: Prof. Mohammad A. Gomaa, Atomic Energy Authority, 3 Ahmad Al-Zomor St., Alzohour District, Nasr City, Children Village Post Office, Postal Code 11787, Cairo, Egypt (fax 00202-287603, email ruatom@rusys.EG.net).

International Symposium on Radiation Technology in Emerging Industrial Applications, Nov. 6-10, 2000, Beijing, China, sponsored by the International Atomic Energy Agency. Contact: IAEA, P.O. Box 100, Vienna International Centre, A-1400 Vienna, Austria (tel + 43 1 2600 21275, fax + 43 1 2600 29610, email official.mail@iaea.org, url www.iaea.org).

First International Symposium on Supercritical Water-Cooled Reactors, Design, and Technology, Nov. 7-8, 2000, Tokyo, Japan, sponsored by the UT Nuclear Engineering Research Laboratory and others. Contact: Mami Yamashita, email mami@tokai.t.u-tokyo.ac.jp.

2000 ANS/ENS International Meeting and Technology Exhibit, Nov. 12-16, 2000, Washington, D.C. Contact: Clyde Jupiter, general chair (tel 301-946-8088, fax 301-946-6539, email clyde_jupiter@jupitercorp.com, url www.ans.org).

Embedded Topical Meeting on Nuclear Applications of Accelerator Technology (AccApp2000), Nov. 12-16, 2000, Washington, D.C., (held in conjunction with ANS/ENS International Meeting and Technology Exhibit), sponsored by the ANS Accelerator Applications Technical Group. Contact: ANS Meetings Department (tel 708-352-6611, fax 708-352-6464, email meetings@ans.org).

International Seminar on Implementation of Systems to Prevent and Detect Unauthorized Uses of Nuclear and Radioactive Materials, Nov. 13-17, 2000, Vienna, Austria, sponsored by the International Atomic Energy Agency. Contact: IAEA, Wagramerstrasse 5, P.O. Box 100, A-1400 Vienna, Austria (tel + 43 1 26000, fax + 43 1 26007, email official.mail@iaea.org, url www.iaea.org).

Fifth International CANDU Maintenance Conference, Nov. 19-21, 2000, Toronto, Ontario, Canada, sponsored by the Canadian Nuclear Society. Contact: CNS, 480 University Ave., Suite 200, Toronto, Ontario, Canada; (tel 416-977-7620, fax 416-977-8131, email cns-snc@on.aibn.com).

Radiation 2000, Nov. 26-28, 2000, Lucas Heights, Australia, sponsored by the Australian Institute of Nuclear Science and Engineering. Contact: Irene Parker, Radiation 2000, PMB 1, Menai NSW 2234 Australia (tel + 02 9717 3436, fax + 02 9717 9268, email ainse@ansto.gov.au, url www.ainse.edu.au/ainse/index.html).

86th Scientific Assembly and Annual Meeting of the Radiological Society of North America, Nov. 26- Dec. 1, 2000, Chicago, IL. Contact: RSNA, (tel 630-571-7850, fax 630-571-7837, email reginfo@rsna.org, url www.rsna.org).
 

December 2000

Fifth Annual Nuclear Congress, Dec. 6-7, 2000, London, England, sponsored by the British Nuclear Energy Society and the British Nuclear Industry Forum. Contact: Sue Frye, ICE Conferences, 1-7 Great George St., London, SW1P 3AA U.K. (tel + 44 20 7665 2315, fax + 44 20 7233 1743, email frye_s@ice.org.uk, url www.bnes.com).

18th Nuclear Particle Physics Conference, Dec. 10-15, 2000, Adelaide, Australia, sponsored by the Australian Institute of Nuclear Science and Engineering. Contact: Irene Parker, AINSE, PMB 1, Menai NSW 2234 Australia (tel + 02 9717 3436, fax +02 9717 9268, email ainse@ansto.gov.au, url www.ainse.edu.au).

International Conference of National Regulatory Authorities with Competence in the Safety of Radiation Sources and the Security of Radioactive Materials, Dec. 11-15, 2000, Buenos Aires, Argentina, sponsored by the International Atomic Energy Agency. Contact: IAEA, IAEA-CN-84, Vienna International Centre, P.O. Box 100, Wagramerstrasse 5, A-1400 Vienna, Austria; (tel +43 1 2600, fax +43 1 26007, email official.mail@iaea.org; url www.iaea.org/worldatom/.)

Symposium Science with Radioactive Beams (PACIFICHEM 2000), Dec. 14-19, 2000, Honolulu, Hawaii, sponsored by the American Chemical Society and others. contact: Congress Secretariat, ACS, (tel 800-227-5558, fax 202-872-6128, email pacifichem@acs.org, url www.acs.org.
 

February 2001

Space Technology and Applications International forum (STAIF-2001), Feb. 11-15, 2001, Albuquerque, NM, sponsored by the Institute for Space and Nuclear Power Studies at the University of New Mexico. Contact: ISNPS-UNM, (tel 505-277-0446, fax 505-277-2814, email isnps@unm.edu, url www-chne.unm.edu/isnps.

Fire and Safety 2001: Fire Protection and Prevention in Nuclear Facilities, Feb. 12-14, 2001, London, England, sponsored by Nuclear Engineering International. Contact: Julie Rossiter, Wilmington Publishing, Ltd., Wilmington House, Church Hill, Wilmington, Dartford, Kent, DA2 7EF, U.K. (tel +44 1322 394706, fax +44 1322 276 743, email conferences@wilmington.co.uk).

Waste Management 2001 Symposium, Feb. 25-Mar. 1, 2001, Tucson, AZ, sponsored by WM Symposia, Inc. Contact: LOI, Inc. (tel 520-292-5652, fax 520-292-9080, email info@laser-options.com, url www.wmsym.org).

Fourth Urals Seminar on Radiation Damage Physics, Feb. 25-Mar. 3, 2001, Snezhinsk, Russia, sponsored by the Institute of Metal Physics. Contact: C.M. Elliott, foreign secretary (tel 217-244-7725, fax 217-244-4293, email cmelliot@uiuc.edu, url www.physics.uiuc.edu/Research/Workshops/ 4th_Urals/.
 

Book . . . Safety Report Series No. 18: Indirect Methods for Assessing Intakes of Radionuclides Causing Occupational Exposure. . . . June 2000 . . . IAEA, Vienna, Austria. . . . IAEA.

Health Phys., 78, 289-294 . . . A Stochastic Model of Radiation-Induced Bone Marrow Damage. . . . Cotlet, G.; Blue, T.E. . . . March 2000 . . . Ohio State University, Columbus, OH.

Health Phys., 78, 295-302 . . . Monte Carlo Calculation of Dose Rate Conversion Factors for External Exposure to Photon Emitters in Soil. . . . Clouvas, A.; Xanthos, S.; Antonopoulos-Domis, M.; Silva, J. . . . March 2000 . . . Aristotle University of Thessaloniki, Thessaloniki, Greece; Universite Pierre et Marie Curie, Paris, France.

Health Phys., 78, 303-310 . . . Verification and Modification of the ICRP-67 Model for Plutonium Dose Calculation. . . . Luciani, A.; Polig, E. . . . March 2000 . . . Forschungszentrum Karlsruhe, Karlsruhe, Germany.

Health Phys., 78, 322-328 . . . Applications of a Quadratic Variance Model for Counting Data. . . . Tries, M.A. . . . March 2000 . . . University of Massachusetts Lowell, Lowell, MA.

Health Phys., 78, 329-331 . . . Non-Invasive Measurement of Water Content in a Lung Phantom by Neutrons. . . . Terrani, S.; Campi, F.; Baccelli, G. . . . March 2000 . . . Polytechnic of Milan, Milano, Italy; Centro di Fisiologia Clinica, Milano, Italy.

Health Phys., 78, 370-376 . . . Environmental Dosimetry Performance Criteria: Pilot Test of Proposed ANSI Draft Standard N13.29. . . . Klemic, G.A.; Shobe, J.; Sengupta, S. . . . April 2000 . . . Environmental Measurements Laboratory, New York, NY; National Institute of Standards and Technology, Gaithersburg, MD; Brookhaven National Laboratory, Upton, NY.

Health Phys., 78, 377-393 . . . Modeling Energy Deposition and Cellular Radiation Effects in Human Bronchial Epithelium by Radon Progeny Alpha Particles. . . . Hofmann, W.; Menache, M.G.; Crawford-Brown, D.J.; Caswell, R.S.; Karam, L.R. . . . April 2000 . . . University of Salzburg, Salzburg, Austria; Duke University Medical Center, Durham, NC; University of North Carolina, Chapel Hill, NC; National Institute of Standards and Technology, Gaithersburg, MD .

Health Phys., 78, 394-413 . . . A Radioiodine Speciation, Deposition, and Dispersion Model with Uncertainty Propagation for the Oak Ridge Dose Reconstruction. . . . Nair, S.K.; Apostoaei, A.I.; Hoffman, F.O. . . . April 2000 . . . The Cadmus Group, Oak Ridge, TN; SENES Oak Ridge, Inc., Oak Ridge, TN.

Health Phys., 78, 414-419 . . . Monte Carlo Calculations of LR115 Detector Response to 222Rn in the Presence of 220Rn. . . . Nikezic, D.; Yu, K.N. . . . April 2000 . . . City University of Hong Kong, Kowloon, Hong Kong; University of Kragujevac, Kragujevac, Yugoslavia.

Health Phys., 78, 420-433 . . . Long-Term Changes in Body Potassium Concentration and Dose from 30K and a Japanese Adult Male Group. . . . Ishikawa, T. . . . April 2000 . . . National Institute of Radiological Sciences, Chiba, Japan.

Health Phys., 78, 476-486 . . . VIP-MAN: An Image-Based Whole-Body Adult Male Model Constructed from Color Photographs of the Visible Human Project for Multi-Particle Monte Carlo Calculations. . . . Xu, X.G.; Chao, T.C.; Bozkurt, A. . . . May 2000 . . . Rensselaer Polytechnic Institute, Troy, NY; Albany Medical College, Albany, NY.

Health Phys., 78, 598-613 . . . Analyzing Bioassay Data Using Bayesian Methods - A Primer. . . . Miller, G.; Inkret, W.C.; Schillaci, M.E.; Martz, H.F.; Little, T.T. . . . June 2000 . . . Los Alamos National Laboratory, Los Alamos, NM.

Health Phys., 78, 614-624 . . . Radionuclides in the Terrestrial Ecosystem Near a Canadian Uranium Mill - Part I: Distribution and Doses. . . . Thomas, P.A. . . . June 2000 . . . University of Saskatchewan, Saskatchewan, Canada.

Health Phys., 78, 625-632 . . . Radionuclides in the Terrestrial Ecosystem Near a Canadian Uranium Mill - Part II: Small Mammal Food Chains and Bioavailability. . . . Thomas, P.A. . . June 2000 . . . University of Saskatchewan, Saskatchewan, Canada.

Health Phys., 78, 633-640 . . . Radionuclides in the Terrestrial Ecosystem Near a Canadian Uranium Mill - Part III: Atmospheric Deposition Rates (Pilot Test). . . . Thomas, P.A. . . . June 2000 . . . University of Saskatchewan, Saskatchewan, Canada.

Health Phys., 78, 648-659 . . . A Generalized Algorithm for Determining the Time of Release and the Duration of Post-Release Radiation Precautions Following Radionuclide Therapy. . . Zanzonico, P.B.; Siegel, J.A.; St. Germain, J. . . . June 2000 . . . Memorial Sloan-Kettering Cancer Center, New York, NY; Nuclear Physics Enterprises, Cherry Hill, NJ.

Health Phys., 78, 660-667 . . . Effects of Time of Administration and Dietary Iodine Levels on Potassium Iodide (KI) Blockade of Thyroid Irradiation by 131I from Radioactive Fallout. . . Zanzonico, P.B.; Becker, D.V. . . . June 2000 . . . Memorial Sloan-Kettering Cancer Center, New York, NY; New York Hospital-Cornell Medical Center, New York, NY.

Health Phys., 78, 693-699 . . . Environmental Distribution and Behavior of 3H and 14C Around Wolsong Nuclear Power Plants. . . . Kim, C-K.; Lee, S-K.; Rho, By-H.; Lee, Y.G. . . . June 2000 . . . Korea Institute of Nuclear Safety, Taejon, Korea; Yosu National University, Yosu, Korea.

Health Phys., 78, 700-710 . . . External Exposure to Radionuclides Accumulated in Shoreline Sediments with an Application to the Lower Clinch River. . . . Apostoaei, A.I.; Nair, S.K.; Thomas, B.A.; Lewis, C.J.; Hoffman, F.O.; Thiessen, K.M. . . . June 2000 . . . SENES Oak Ridge, Inc., Oak Ridge, TN.

Health Phys., 78, 711-715 . . . Determination of Optimum Time Interval of Meteorological Data Used with Atmospheric Dose Modeling at SRS. .. Simpkins, A.A.; Parker, M.J.; Weber, A.H. . . June 2000 . . . Westinghouse Savannah River Co., Aiken, SC.

Health Phys., 78, 716-720 . . . A Comparison Between Default EGS4 and EGS4 with Bound Compton Cross Sections When Scattering Occurs in Bone and Fat. . . . Marianno, C.M.; Higley, K.A.; Palmer, T.S. . . . June 2000 . . . Oregon State University, Corvallis, OR.

Health Phys., 78, 727-738 . . . The Assessment of the Effect of Thyroid Size and Shape on the Activity Estimate Using Monte Carlo Simulation. . . . Kramer, G.H.; Crowley, P. . . . June 2000 . . . Human Monitoring Laboratory, Ontario, Canada.

Health Phys., 78, 739-743 . . . The Uncertainty in the Activity Estimate from a Lung Count Due to the Variability in Chest Wall Thickness Profile. . . . Kramer, G.H.; Crowley, P.; Burns, L.C. . . . June 2000 . . . Human Monitoring Laboratory, Ontario, Canada.

Health Phys., 79, 15-23 . . . Reconstruction of Radionuclide Contamination of the Techa River Caused by Liquid Waste Discharge from Radiochemical Production at the Mayak Production Association . . . Mokrov, Y.; Glagolenko, Y.; Napier, B. . . . July 2000 . . . Mayak Central Laboratory, Chelyabinsk Oblast, Russia; Pacific Northwest National Laboratory, Richland, WA.

Health Phys., 79, 24-35 . . . The Techa River Dosimetry System: Methods for the Reconstruction of Internal Dose. . . . Degteva, M.O.; Kozheurov, V.P.; Tokstykh, E.I.; Vorobiova, M.I.; Anspaugh, L.R.; Napier, B.A . . . July 2000 . . . Urals Research Center for Radiation Medicine, Chelyabinsk, Russia; University of Utah, Salt Lake City, UT; Battelle Pacific Northwest Laboratory, Richland, WA; Research Institute of Industrial and Marine Medicine, St. Petersburg, Russia.

Health Phys., 79, 36-47 . . . Radioecological Impacts of the Techa River Contamination. . . . Akleyev, A.V.; Kostyuchenko, V.A.; Peremyslova, L.M.; Baturin, V.A.; Popova, I.Ya. . . . July 2000 . . . Urals Research Center for Radiation Medicine, Chelyabinsk, Russia.

Health Phys., 79, 48-54 . . . Deterministic Effects from Occupational Radiation Exposures in a Cohort of Mayak PA Workers: Data Base Description. . . . Claycamp, H.G.; Okladnikova, N.D.; Azizova, T.V.; Belyaeva, Z.D.; Boecker, B.B.; Pesternikov . . . July 2000 . . . University of Pittsburgh, Pittsburgh, PA; Branch No. 1 of the Biophysics Institute, Chelyabinsk Region, Russia; Lovelace Respiratory Research Institute, Albuquerque, NM; Mayak Production Association, Chelyabinsk Region, Russia.

Health Phys., 79, 55-62 . . . Stochastic Effects of Environmental Radiation Exposure in Populations Living Near the Mayak Industrial Association: Preliminary Report on Study of Cancer Morbidity . . . Kossenko,M.M.; Hoffman, D.A.; Thomas, T.L. . . . July 2000 . . . Urals Research Center for Radiation Medicine, Chelyabinsk, Russia; The George Washington University, Washington, DC; Uniformed Services University of the Health Sciences, Bethesda, MD.

Health Phys., 79, 63-71 . . . Metabolism and Dosimetry of Actinide Elements in Occupationally-Exposed Personnel of Russia and the United States: A Summary Progress Report. . . . Khokhryakov, V.F.; Suslova, K.G.; Gilipy, R.E.; Alldredge, J.R.; Aladova, E.E.; Glover, S.E. . . . July 2000 . . . Branch No. 1, Federal Research Center Institute of Biophysics, Chelyabinsk Region, Russia; Washington State University-Tricities, Richland, WA; Washington State University, Pullman, WA.

Health Phys., 79, 72-76 . . . Development of an Improved Dosimetry System for the Workers at the Mayak Production Association. . . . Khokhryakov, V.; Suslova, K.; Aladova, E.; Vasilenko, E.; Miller, S.C.; Slaughter, D.M.; Kra . . . July 2000 . . . Branch No. 1, Federal Research Center Biophysics Institute, Chelyabinsk Region, Russia; Mayak Production Association, Chelyabinsk Region, Russia; University of Utah, Salt Lake City, UT.

Health Phys., 79, 121-128 . . . The 1999 Lauriston S. Taylor Lecture - Back to Background: Natural Radiation and Radioactivity. . . . Harley, N.H. . . August 2000 . . . New York University School of Medicine, New York, NY.

Health Phys., 79, 129-135 . . . Evaluation of Uncertainties in Estimates of Fetal Doses from 59Fe Kinetic Studies at Vanderbilt University. . . Moeller, D., Merwin, S.E. . . . August 2000 . . . Dade Moeller & Assoc., New Bern, NC, and Richland, WA.

Health Phys., 79, 136-146 . . . Personnel Exposure During Gamma Endovascular Brachytherapy. . . Balter, S.; Oetgen, M.; Hill, A.; Dalton, J.; Sacher, A.; Lipsztein, R.; Collins, M.; Moses, . . August 2000 . . . Lenox Hill Heart & Vascular Institute of New York, New York, NY.

Health Phys., 79, 147-153 . . . The Impact of Plutonium Speciation on the Distribution Coefficients in a Sediment - Sea Water System, and Radiological Assessment of Doses to Humans. . . . Skipperud, L.; Oughton, D.H.; Salbu, B. . . . August 2000 . . . Agricultural University of Norway, Aas, Norway.

Health Phys., 79, 170-181 . . . Wendi: An Improved Neutron REM Meter. . . . Olsher, R.H.; Hsu, H-H., Beverding, An.; Kleck, J.H.; Casson, W.H.; Vasilik, D.G.; Devine, R . . . August 2000 . . . Los Alamos National Laboratory, Los Alamos, NM; Ancore/SAIC, Santa Clara, CA; Varian Assoc., Palo Alto, CA.

Health Phys., 79, 199-202 . . . Does Body Size Contribute to Sensitivity of Bone Tumor Induction by Radionuclide Exposure? . . . Lloyd, R.D.; Taylor, G.N.; Miller, S.C. . . . August 2000 . . . University of Utah, Salt Lake City, UT.

Health Phys., 79, 203-206 . . . Chest Wall Thickness Measurements of the LLNL Phantom For Small Area Germanium Detector Counting. . . . Kramer, G.H.; Lee, T-Y.; Chang, S-Y. . . . August 2000 . . . Human Monitoring Laboratory, Ontario, Canada.; Korea Atomic Energy Research Institute, Taejon, Korea.

Nucl. Sci. Eng., 134, 239-264 . . . A Comparison of Angular Difference Schemes for One-Dimensional Spherical Geometry Sn Equations. . . . Lathrop, K.D. . . . March 2000 . . . Stanford Linear Accelerator Center, Stanford, CA.

Nucl. Sci. Eng., 134, 293-305 . . . A Best-Estimate Reactor Core Monitor Using State Feedback Strategies to Reduce Uncertainties. . . . Martin, R.P.; Edwards, R.M. . . . March 2000 . . . Siemens Power Corp., Richland, WA;, Pennsylvania State University, University Park, PA.

Nucl. Sci. Eng., 134, 306-311 . . . Some Comments on the Behavior of the RELAP5 Numerical Scheme at Very Small Time Steps. . . . ; Tiselj, I.; Cerne, G. . . . March 2000 . . . Jozef Stefan Institute, Ljubljana, Slovenia.

Nucl. Sci. Eng., 135, 103-122 . . . Differential Sampling Applied to Mammography Image Simulation. . . . ; Peplow, D.E.; Verghese, K. . . . June 2000 . . . Oak Ridge National Laboratory, Oak Ridge, TN; North Carolina State University, Raleigh, NC.

Nucl. Sci. Eng., 135, 123-140 . . . Neutron Transport in Spatially Random Media: An Assessment of the Accuracy of First Order Smoothing. . . . Williams, M.M.R. . . . June 2000.

Nucl. Sci. Eng., 135, 141-149 . . . New High-Resolution Fission Cross-Section Measurements of 233U in the 0.4-eV to 700-keV Energy Range. . . . Guber, K.H.; Spencer, R.R. Leal, L. C.; Harvey, J.A.; Hill, N.W.; Dos Santos, G.; Sayer, R.O . . . June 2000 . . . Oak Ridge National Laboratory, Oak Ridge, TN.

Nucl. Sci. Eng., 135, 190-198 . . . On the Curvature of Transmitted Intensity Plots in Broad Beam Studies. . . . El-Kateb, A.H. . . . June 2000 . . . Helwan University, Cairo, Egypt.

Nucl. Technol., 128, 12-24 . . . Rapid-A Fast Reactor Concept Without Any Control Rods. . . . Kambe, M. . . . October 1999 . . . Central Research Institute of Electric Power Industry, Tokyo, Japan.

Nucl. Technol., 128, 25-34 . . . Radiological Impact at the Extraction Stage of the Thorium Fuel Cycle. . . . Schapira, J.P.; Singhal, R.K. . . . October 1999 . . . Institut de Physique Nucleaire, Orsay Cedex, France.

Nucl. Technol., 128, 35-45 . . . Fuel Element Burnup Determination in Mixed Triga Core Using Reactor Calculations. . . . Ravnik, M.; Zagar, T.; Persic, A. . . . October 1999 . . . Institute Jozef Stefan, Ljubljana, Slovenia.

Nucl. Technol., 128, 124-130 . . . Multinodal Treatment of Production, Decay, and Spreading of Radioactive Isotopes. . . . Vertes, P. . . . October 1999 . . . FKFI Atomic Energy Research Institute, Budapest, Hungary.

Nucl. Technol., 128, 131-138 . . . Overview of RETRAN Related Activities. . . . Agee, L.J. . . . November 1999 . . . Electric Power Research Institute, Palo Alto, CA.

Nucl. Technol., 128, 139-152 . . . Implementation of an Improved Interfacial Mass and Energy Transfer Model in RETRAN-3D. . . . Macian, R.; Cebull, P.; Coddington, P.; Paulsen, M. . . . November 1999 . . . Paul Scherrer Institute, Villigen PSI, Switzerland; Computer Simulation & Analysis, Inc., Idaho Falls, ID.

Nucl. Technol., 128, 153-168 . . . Evaluation of the Slip Options in RETRAN-3D. . . . Maier, D.; Coddington, P. . . . November 1999 . . . Paul Scherrer Institute, Villigen PSI, Switzerland.

Nucl. Technol., 128, 169-185 . . . Tenth Cofrentes Reload Licensing Analysis with RETRAN-03 Methodology. . . . De la Fuente, R.; Dey, J.M.; Sedano, P.G.; Mata, P. . . . November 1999 . . . IBERDROLA Engineering and Consulting, Madrid, Spain.

Nucl. Technol., 128, 186-204 . . . Analyses of Startup Test, Reload Limiting Transient, and Plant Event for the Kuosheng BWR-6 Related to MSIV Closure. . . . Tang, J-R.; Ma, S-S.; Wang, J-D.; Chiang, S-C.; Chou, L-Y.; Yao, C-C.; Liao, Y-T. . . . November 1999 . . . Institute of Nuclear Energy Research, Taoyuan, Taiwan; Taiwan Power Company, Taipei, Taiwan.

Nucl. Technol., 128, 205-215 . . . Modeling and Simulation of the First ABWR for Validation of RETRAN-3D. . . . Mori, M. . . . November 1999 . . . Tokyo Electric Power Company, Inc., Yokohama, Japan.

Nucl. Technol., 128, 216-224 . . . Mihama Unit 2 Steam Generator Tube Rupture Analysis. . . . Tamaki, T.; Ohtani, M.; Kawabe, Y. . . . November 1999 . . . Institute of Nuclear Safety System, Inc., Fukui, Japan.

Nucl. Technol., 128, 225-232 . . . VIPRE-02 Subchannel Validation Against NUPEC BWR Void Fraction Data. . . . Aounallah, Y.; Coddington, P. . . . November 1999 . . . Paul Scherrer Institute, Villigen, PSI, Switzerland.

Nucl. Technol., 128, 233-244 . . . Main-Steam-Line-Break Analysis of TMI-1 Using RETRAN-3D. . . . Peterson, C.E.; Shatford, J.G.; Irani, A.; Trikouros, N.G.; Dias, A.F.; Agee, L.J. . . . November 1999 . . . Computer Simulation & Analysis, Inc., Idaho Falls, ID; GPU Nuclear Corp., Parsippany, NJ; S. Levy, Inc., Campbell, CA; Electric Power Research Institute, Palo Alto, CA.

Nucl. Technol., 128, 245-256 . . . Plutonium Recycling in a Full-Mox 900-MW (electric) PWR: Physical Analysis of Accident Behaviors. . . . Aniel-Buchheit, S.; Puill, A.; Sanchez, R.; Coste, M. . . . November 1999 . . . Commissariat a l'Energie Atomique (CEA), Gif sur Yvette, France.

Nucl. Technol., 128, 257-275 . . . A Study on Regional Stability Analysis Methodology with a One-Point Neutron Kinetics Model. . . . Takeuchi, Y.; Takigawa, Y.; Miyamoto, S. . . . November 1999 . . . Toshiba, Corp., Kawasaki, Japan; Toshiba Corp., Yokohama, Japan.

Nucl. Technol., 128, 276-283 . . . Application of Neutral Networks to Analyze Load-Follow Operation in a Pressurized Water Reactor. . . . Seong, S.H.; Lee, U.C.; Kim, S.H.; Jang, J.W. . . November 1999 . . . Korea Atomic Energy Research Institute, Taejon, Korea; Seoul National University, Seoul, Korea.

Nucl. Technol., 129, 1-12 . . . First In-Pile Experimental Results of High-Plutonium-Content Oxide Fuel for Plutonium Burning in Fast Reactors. . . . ; Picard, E.; Noirot, J.; Moss, R.L.; Plitz, H.; Richter, K.; Rouault, J. . . . January 2000 . . . Commissariat a l'Energie Atomique, Paul-lez-Durance, France; Joint Research Center, Petten, The Netherlands; Forschungszentrum Karlsruhe, Karlsruhe, Germany; Institute for Transuranium Elements, Karlsurhe, Germany; Commissariat a l'Energie Atomique, Paul-lez-Durance, France.

Nucl. Technol., 129, 26-35 . . . A Nodal Kinetics and Thermohydraulics Analysis (NOKTA) Code for Analyzing Rod-Ejection Accidents and Other Transients in Nuclear Power Reactor Cores. . . . Kaya, S.; Yavuz, H. . . . January 2000 . . . Cekmece Nuclear Research and Training Center, Istanbul, Turkey; Istanbul Technical University, Istanbul, Turkey.

Nucl. Technol., 129, 285-296 . . . Neutron Fluence, Dosimetry and Damage Response Determination in In-Core/Ex-Core Components of the Venus CEN/SCK LWR Using 3-D Monte Carlo Simulations: NEA's Venus-3 Benchmark . . . Perlado, J.M.; Marian, J.; Sanz, J.G. . . . March 2000 . . . Instituto de Fusion Nuclear, Madrid, Spain.

Nucl. Technol., 129, 407-417 . . . A Novel Method for Energy Production Using 242mAm as a Nuclear Fuel. . . . Ronen, Y.; Aboudy, M. Regev, D. . . . March 2000 . . . Ben-Gurion University, Beer-Sheva, Israel.

Nucl. Technol., 131, 12-21 . . . Theoretical Derivation of Simplified Evaluation Models for the First Peak of a Criticality Accident in Nuclear Fuel Solution. . . . Nomura, Y. . . . July 2000 . . . Japan Atomic Energy Research Institute, Ibaraki-ken, Japan.

Nucl. Technol., 131, 22-35 . . . Fission-Product Release During Transient Heating of Irradiated Candu Fuel. . . . Liu, Z.; Dickson, R.S.; Dickson, L.W.; Bilanovic, Z.; Cox, D.S. . . . July 2000 . . . Atomic Energy of Canada Ltd., Ontario, Canada.

Nucl. Technol., 131, 36-47 . . . Fission Product Release Behavior of Individual Coated Fuel Particles For High-Temperature Gas-Cooled Reactors. . . . Minato, K.; Sawa, K.; Koya, T.; Tomita, T.; Ishikawa, A.; Baldwin, C.A.; Gabbard, W.A.; Mal . . . July 2000 . . . Japan Atomic Energy Research Institute, Ibaraki-ken, Japan; Oak Ridge National Laboratory, Oak Ridge, TN.

Nucl. Technol., 131, 153-158 . . . The Impact of the Steam-Water Mixture Heterogeneity on the Results of Boiling Water Reactor Cell Calculations. . . . Goltsev, A.O.; Martynov, D.N.; Marin, S.V.; Lekomtsev, A.A. . . . August 2000 . . . Kurchatov Institute, Moscow, Russia; Bauman Moscow State Technical University, Moscow, Russia.

Nucl. Technol., 131, 159-196 . . . Development of a Code With the Capability of Internal Assessment of Uncertainty. . . . D'Auria, F.; Giannotti, W. . . . August 2000 . . . Universita di Pisa, Pisa, Italy.

Nucl. Technol., 131, 197-209 . . . Parametric Studies on Plutonium Transmutation Using Uranium-Free Fuels in Light Water Reactors. . . Shelley, A.; Akie, H.; Takano, H.; Sekimoto, H. . . . August 2000 . . . Tokyo Institute of Technology, Tokyo, Japan; Japan Atomic Energy Research Institute, Ibaraki-ken, Japan.

Nucl. Technol., 131, 210-227 . . . Calculated Actinide and Fission Product Concentration Ratios for Gaseous Effluent Monitoring Using MONTEBURNS 3.01. . . . Charlton, W.S.; Perry, R.T.; Fearey, B.L.; Parish, T.A. . . . August 2000 . . . Los Alamos National Laboratory, Los Alamos, NM; Texas A&M University, College Station, TX.

Nucl. Technol., 131, 228-238 . . . VVER1000/320 Operational Transient Simulation with the CATHARE Computer Program. . . . Troshko, A.A.; Hassan, Y.A. . . . August 2000 . . . Texas A&M University, College Station, TX.

Nucl. Technol., 131, 239-251 . . . Localization of a Vibrating Control Rod Pin in Pressurized Water Reactors Using the Neutron Flux and Current Noise. . . . Arzhanov, V.; Pazsit, Im. Garis, N.S. . . . August 2000 . . . Chalmers University of Technology, Goteborg, Sweden.

Nucl. Technol., 131, 252-268 . . . Rethinking High-Level Waste Disposal: Separate Disposal of High-Heat Radionuclides (90Sr and 137Cs). . . . Forsberg, C.W. . . . August 2000 . . . Oak Ridge National Laboratory, Oak Ridge, TN.

Nucl. Technol., 131, 269-276 . . . Prediction of In-Phantom Dose Distribution Using in-Air Neutron Beam Characteristics for Boron Neutron Capture Synovectomy. . . . Verbeke, J.M.; Chen, A.S.; Vujic, J.L.; Leung, K-N. . . . August 2000 . . . University of California, Berkeley, CA; Lawrence Berkeley National Laboratory, Berkeley, CA.