William C. Hopkins, ANS member since
1975, was awarded the Standards Service Award. Hopkins, of Bechtel Power
Corp., was recognized for "his outstanding contributions to the society's
Standards Committee, particularly for his leadership as chairman of ANS-6,
Radiation Protection and Shielding, and for his dedicated services as a
member of N17 and the Standards Steering Committee."
Professor Emeritus Allan F. Henry, 76, of nuclear engineering, who came to MIT as a visiting professor in 1968 and stayed for 32 years, died of kidney failure at the MIT infirmary on January 28.
Professor Henry earned the BS in chemistry (1945), and the MS (1947) and PhD (1950) in physics, all from Yale University. Upon graduation from Yale, Professor Henry volunteered to drive an ambulance with the British troops in India after knee injuries precluded him from serving in the US Army. After the war, he joined the Bettis Atomic Power Laboratory as a senior scientist. From 1954-69 he was the manager of reactor theory and methods at Bettis.
Professor Henry, who developed mathematical models to describe neutron behavior in reactors, retired in 1995 but continued to teach until 1999. He was a member of the American Nuclear Society and wrote the book Nuclear Reactor Analysis (MIT Press, 1975). He chaired the Department of Nuclear Engineering Committee on Graduate Students and served on the Committee on Graduate School Policy.
A Boston resident, Professor Henry twice won the Outstanding Teacher Award in nuclear engineering (1974 and 1986). He received the E.P. Wigner Award from the American Nuclear Society and the Technical Achievement Award from the Reactor Physics and Mathematics and Computation Division of the American Nuclear Society, both in 1992.
He was a fellow of the American Nuclear Society and served on its board of directors. He was elected to the National Academy of Engineering in 1985 and served on advisory boards to several national laboratories.
Born in Philadelphia on January 12, 1925, Professor Henry was an accomplished classical pianist as a child, receiving several awards for his artistry, including the Pressor Award and the Chopin Award.
He is survived by two brothers, E. James Jr. of Dallas and Thomas H. of Huntington, WV. His family suggests donations in his honor be made for a worthy student in the Department of Nuclear Engineering. An MIT memorial service will be scheduled for the spring.
OP SYS: Windows
J. Stewart Bland Associates, Inc., Annapolis, Maryland, contributed this suite of NRC's computer codes (LADTAP II, GASPAR II, and XOQDOQ) used for evaluating routine radioactive effluents from nuclear power plants with a WINDOWS interface to facilitate ease of use. NRCDose 2.2.3 is intended for modeling routine, normal effluents under annual average environmental conditions and should not be used for accident dose assessment. The liquid pathway dose assessments of the LADTAP II code are based on the modeling presented in NRC Regulatory Guide 1.109, Rev. 1, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I." GASPAR II, the gaseous pathway dose assessment, is also based on Regulatory Guide 1.109 modeling. XOQDOQ, presenting the meteorological dispersion calculations, is based in the modeling of Regulatory Guide 1.111, Rev. 1, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors." The technical references for these programs are NUREG/CR-1276 "User's Manual for LADTAP II;" NUREG/CR-4653 "GASPAR II - Technical Reference and User Guide;" and NUREG/CR-2919 "XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations."
NRCDose runs on IBM PC Pentium type computers.
The distributed executables runs under the Windows operating system, and
Fortran source files are not included. 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
OP SYS: Unix, DOS
Los Alamos National Laboratory, Los Alamos, New Mexico, recommended an update to MCNP4C, which is a general-purpose, continuous-energy, generalized geometry, time-dependent, coupled neutron-photon-electron Monte Carlo transport code system. The install.fix file was replaced, so that a desired datapath may be added and MDAS (length of storage for the static memory option) may be changed with the MCNP installation feature. Unix users may download the revised install.fix file from the developer's website at LANL or from the MCNP4C electronic notebook on the RSICC web site:
The Lahey/Fujitsu Fortran 95 Compiler Release 5.50d was used to build MCNP executables with MDAS=4,000,000, MDAS=8,000,000 and MDAS=32,000,000.
MCNP is operable on Cray computers under UNICOS, workstations or PC's running Unix or Linux, Windows NT/9x PC's, and Vax computers under VMS. Compilation requires both Fortran 77 and ANSI C standard compilers. The source can be compiled with g77 on PC's running Red Hat Linux. RSICC tested this release on several Unix workstations (IBM RS/6000, Sun, HP, DEC, and SGI); on a Pentium III running Redhat Linux Version 6.1; on a Pentium II in a DOS window of Windows 98 with Digital Visual Fortran Professional Edition 6.0A Fortran 90 compiler with QuickWin plots; and on a Pentium II with Lahey/Fujitsu Fortran 95 Version 5.50 compiler with Winteracter Starter Kit.
The electronic documentation, source codes,
test problems, executables, and installation scripts are distributed on
CD-ROM and can be read under either Windows or UNIX operating systems.
As a convenience to users, the DLC-200/MCNPDATA library is included on
the distribution media. The cross sections are in ASCII mode in the Unix
file and in binary mode for PC Windows users. The package is transmitted
on CD in both Unix and DOS compressed formats. References: Readme.txt (April
2000) and LA-13709-M (April 2000). Fortran 77 or 90 and C; Unix workstations,
Intel-based Pentium, Cray, and Vax. (C00700/ALLCP/02).
OP SYS: Unix, DOS
A Windows version of the Monte Carlo n-particle transport code system for multiparticle and high energy applications was added to the MCNPX Unix package. MCNPX was developed by the Accelerator Production of Tritium Technical Project Office, Los Alamos National Laboratory, Los Alamos, New Mexico. Tom Jordan of Experimental Physics and Mathematics Consultants converted the LANL MCNPX Unix programs to create a Windows PC version and contributed it to RSICC. The MCNPX code developers at LANL use Unix (including Linux) systems and are not familiar with the Windows implementation, so no support from the LANL developers is available for the Windows application.
The official date of the programs in this release of MCNPX 2.1.5 is "Thu Mar 16 17:31:45 MST 2000." 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 executes on many computers running
Unix operating systems. The Lahey F90 Version 4.50 compiler was used to
create the executables included in the new Windows version which has run
under Windows95, Windows98, WindowsNT4/sp3, and Windows2000. Source files
for the Windows version are not distributed. At RSICC the executables were
tested on a Pentium III running Windows NT4, Service Pack 6. The package
is transmitted on one distribution CD which contains full source code for
the MCNPX Unix system and test sets for each of the supported architectures
in a compressed Unix tar file. The PC executables and test cases are included
in self-extracting compressed DOS files. The DLC-205/MCNPXDATA library
is included on the MCNPX distribution CD as a convenience to users. Reference:
TPO-E83_G-UG-X-00001, Rev. 0 (November 14, 1999). Fortran 77 and C. Cray
Unicos, IBM RS/6000 AIX, DEC Alpha Digital Unix, SGI, HP, Sun, Intel I386
Linux, Windows-based PC's (C00705/MNYCP/01).
OP SYS: VMS
Lawrence Livermore National Laboratory Livermore, California, through the OECD NEA Data Bank, Issy-les-Moulineaux, France, contributed this code system for computerized quantitative analysis by gamma-ray spectrometry. GAMANAL provides a complete qualitative and quantitative analysis of mixtures of radioactive species such as fission products by computer interpretation of high-resolution gamma-ray spectra. The program first determines and removes the background or Compton continuum under the peaks in a spectrum to locate the peak regions. This is done by examining the pulse-height spectrum data for background and peak regions and then fitting these data with the proper shape functions. When determining the photon emission rate, corrections are made for the effects of geometry, attenuation, and detector efficiency. Nonlinearities in the equipment are taken into account in setting up the energy scale.
GAMANAL was tested on a VAX-11/780 under
VMS V4.4 in 1988 and was not tested when it was contributed to RSICC in
February 2001. A Vax Fortran 77 compiler is required. The source files
in this package will require modifications to run on other computers. The
package is transmitted as a self-extracting compressed file on a DS/HD
diskette, which contains the Fortran source and sample problem. After file
decompression, there are 230 files that are about 1.79 MB. References:
UCRL-51061, Vol. I (March 1972) and UCRL-51061, Vol. IV (June 1972). Fortran
77; DEC VAX11/750 and DEC VAX11/780 (P00506/D0VAX/00).
CHANGES TO THE DATA LIBRARY COLLECTION
Two data libraries of the collection were updated during the month.
OP SYS: Unix, DOS
Los Alamos National Laboratory, Los Alamos, New Mexico, contributed a revision to URES, which is included this comprehensive set of cross sections for a wide range of in radiation transport applications for use with the Monte Carlo code package CCC-700/MCNP4C.
URES is a neutron cross-section library for MCNP and MCNPX that includes probability tables to represent unresolved resonances. Processing problems were found for 6 of the isotopes in URES: W-182, W-183, W-184, W-186, Th-232, and U-238. The problems would impact coupled neutron-photon calculations; neutron only problems would not be affected. An updated version of URES, named URESA, has been prepared. For the 6 isotopes listed above, the photon-production data were deleted, and the ZAID's were changed from .49c to .48c. Users should note that the heating (energy-deposition) data are now inconsistent for these isotopes and should not be used. The other 21 isotopes have simply been copied over intact from URES to URESA and their ZAIDs remain .49c. All of the data on URESA will be superseded by data on the ENDF66 library, a major new release planned for later in 2001.
All data libraries in the Unix tar file are in ASCII format and can be used with MCNP4C on all computer platforms supported by the code. Files distributed in compressed mode on the distribution CD can be read under either Windows or Unix. A self-extracting compressed file for Windows users contains both the MCNP4C code system with executables and cross-sections from MCNPDATA in binary format for PC users. Expanding the code system (50 MB) and binary cross section libraries (360MB) under Windows requires ~410 MB of hard disk space. Unix users need more because the ASCII cross sections require 880 MB of hard disk space.
References: The following documents are distributed
in electronic (PDF) form with the package: Revised Appendix G of the MCNP4C
manual, README (April 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). (D00200/ALLCP/02)
OP SYS: Unix, DOS
Los Alamos National Laboratory, Los Alamos, New Mexico, contributed a revision to URES which is included in 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 Version 4B, 4C and later of the MCNP transport code. This data package provides a comprehensive set of cross sections for a wide range of radiation transport applications using the MCNPX Monte Carlo code package.
As noted in the announcement of DLC-200/MCNPDATA above, URES was replaced with a revision designated URESA. Note that MCNPX does not currently use the probability tables. Previously the MCNPXDATA package was available only in tar format. A Windows version of MCNPX 2.1.5 is being released this month, so the ASCII MCNPDATA libraries were downloaded for use with the new PC release.
All data libraries are distributed in compressed
mode. Expanded files are in ASCII format and can be used with MCNPX on
all computer platforms supported by the code. The data are distributed
on CD in a GNU compressed tar file and in a self-extracting compressed
file for use under Windows on PC. References: The following documents are
distributed in electronic (PDF) form with the package: Revised 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/01)
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.
A detailed program is available from the web page. Lectures and computer applications will be introduced alternately. Both will be given by the principal code developer Dr. Nancy Larson (ORNL, USA). Topics include:
The workshop will include several hands-on computer applications using the latest version of SAMMY (M5). Computer exercises will lead participants through the various features of the code, beginning with simple examples and leading to realistic situations. Participants are encouraged to bring their own examples as well.
For further information, contact: Dr. Ali
NOURI, OECD/NEA Data Bank (tel: 33-1-184.108.40.206, fax: 33-1-220.127.116.11,
e-mail: email@example.com). Please
see their web page for more detailed information: http://www.nea.fr/html/dbdata/sammy/workshops/april2001.
Location: Instituto Superior Tecnico, Lisbon, Portugal
Contact: Inquiries should be addressed to Ms. Sandra Oliveira, (tel +351-21-8419092, fax +351-21-8419143, email NRAD2001@CFIF.IST.UTL.PT).
The aim of the school is to bring together fundamental issues of nuclear radioactivity and nuclear astrophysics as well as some of the technological applications. The indicators show that sciences with a strong social impact will occupy a predominant position in the turn of the century. Nuclear physics is one of the branches of science that is expected to play an important role in this new era. On the other hand, astrophysics has always been an attraction to the human mind. Here, nuclear physics has an essential part. It is thus timely that the nuclear physics community participates actively, either addressing fundamental questions, or applying its knowledge to astrophysics and practical aspects of our society.
There will be a set of invited talks, addressing the most burning issues within the topics of the school, in a format that will allow the participant to get acquainted with some basic ideas, and simultaneously learn about the most recent developments. There will also be some invited seminars and selected short contributions.
A one-page abstract, in LaTex form, is required
for the selection of oral contributions. It must be sent by e-mail to NRAD2001@CFIF.IST.UTL.PT.
The deadline for the submission of abstracts is June 1. The final decision
will be communicated before June 30. The registration fee is 35 000 PTE.
It includes coffee breaks, the welcome reception, the school banquet and
a copy of the proceedings. Payment must be done on arrival. The deadline
for registration is July 31. More information on the school is available
on the web at: http://cfif.ist.utl.pt/~nrad2001.
Introductory classes are for people who have little or no experience with MCNP. The classes survey the features of MCNP so the beginning user will be exposed to the capabilities of the program, and will have hands-on experience at running the code to solve rudimentary problems. Course topics include Basic Geometry, Source Definitions, Output (Tallies) Specification and Interpretation, Advanced Geometry (repeated structures specification), Variance Reduction Techniques, Statistical Analysis, Criticality, Plotting of Geometry, Tallies, and Particle Tracks, and Neutron/Photon/Electron Physics.
NOTE: While MCNP supports a number of platforms, class computers are usually Unix machines. Experience with Unix will be helpful to the student but is not essential.
Costs For Domestic U.S. Classes: Cost for the class is $1,800. There is a $300 discount if payment is received by the close of registration/early payment deadline for each class. Radiation Safety Information Computational Center (RSICC) provides the code and data package and documentation for a reduced fee of $310 to all who complete the class and free to students employed by sponsors that fund RSICC.
The class fee includes a notebook with all class viewgraphs (over 300) and handouts. Dinner the first evening is included as part of your registration fee and snacks and refreshments are provided during class breaks. Lodging will be available for roughly $75 per night. Information will be sent by follow-up letter or email when we receive your registration information.
All classes provide interactive computer
learning. Time will be available to discuss individual questions and problems
with MCNP experts. To register for the LANL classes via the Internet, go
For registration information on the European classes, contact Enrico Sartori,
OECD/NEA at firstname.lastname@example.org.
DATES: May 14-18, 2001
FEE: $1,700 per person (includes the MCNP™ code package). Price subject to change without notice. Payments must be received at least 45 days before class. If payment has not been received by the due date, your space may be given up to the next available person on our waiting list. Refunds are available up to 30 days before the class date.
PLACE: The Canyon School Complex, Los Alamos National Laboratory, Los Alamos, New Mexico.
Contacts: Inquiries regarding registration and class space availability should be made to David Seagraves, 505-667-4959, fax: 505-665-6071, e-mail: email@example.com. Technical questions may be directed to Dick Olsher, 505-667-3364, e-mail: firstname.lastname@example.org. For further information and registration on the Internet, visit: http://drambuie.lanl.gov/~esh4/mcnp.htm.
The Los Alamos MCNP code is a general and powerful Monte Carlo transport code for photons, neutrons, and electrons. MCNP can be safely described as the "industry standard" with more than 600 person-years of development effort behind it. It is supported on a variety of platforms and is now accessible to Health Physicists, Medical Physicists, and Rad Engineers using desktop or laptop personal computers. This 4.5 day course introduces the basic concepts of Monte Carlo, demonstrates how to put together a MCNP input file, and illustrates some health and medical physics applications of the code. No prior knowledge of Monte Carlo is assumed.
MCNP is ideally suited to the needs of professionals interested in performing radiation shielding and skyshine calculations, detector simulation studies, or dosimetry. With a little practice and study of the examples, many will find they are able to solve problems that have, in the past, been out of reach. Problems that involve a complex geometry can be easily solved using MCNP (e.g., designing a maze entrance to a radiation room). Calculations are based on detailed physics models and very accurate cross section tables that require no energy group compromises to be made.
A copy of the MCNP code package is included in the price of the course. Your copy of MCNP will be provided directly from the Radiation Safety Information Computational Center (RSICC) at Oak Ridge. Only RSICC is authorized to distribute licensed copies of the MCNP code package. All of the input and output files for the class demonstrations will be provided for self-study on a diskette. The course will focus on providing a practical boost toward learning the program and guiding the student toward useful applications. Extensive practice sessions are scheduled using a personal computer in class.
The course will be taught by Dick Olsher
and David Seagraves of the Health Physics Measurements Group, Los Alamos
National Laboratory. Additional staff help will be provided by members
of the Health Physics Measurements Group. Students will 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.
Visual Editor Classes Offered
The Visual Editor is a powerful visualization tool that can be used to rapidly create complex Monte Carlo N Particle (MCNP 4C) geometry models, including lattices, universes, fills, and other geometrical transformations. The Visual Editor can:
Display MCNP 4C geometries in multiple plot
A three-day class is to be held October 8-10,
2001, in Richland, Washington. This class will only focus on the use
of the visual editor. Users should already be familiar with the use of
MCNP. 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 or Windows NT version
if it is working by then. Attendees are encouraged to bring their own input
files for viewing and modifying in the visual editor. Further information
on this class can be located at:
or by contacting: Randy Schwarz at 509-372-4042 or email: email@example.com.
Class size is limited and courses are subject to cancellation if minimum enrollment is not obtained one month prior to the course. Course fees are refundable up to one month before each class. Classes are cosponsored by RSICC. Foreign nationals must register at least six weeks in advance. For further information, contact Kay at 865-574-9213 or visit the web, http://www.cped.ornl.gov/scale/ trcourse.html.
SCALE Shielding and Source Terms Course (April 23-27, 2001) and (October 15-19, 2001)
The SCALE Shielding and Source Terms Course
emphasizes SAS2 and ORIGEN-ARP (depletion/source-term generation) and SAS3
and SAS4 using MORSE-SGC (3-D Monte Carlo neutron/gamma shielding). It
also covers SAS1/XSDRNPM (1-D neutron/gamma shielding) and QADS/QAD-CGGP
(3-D point kernel gamma shielding).
SCALE KENO-VI Criticality Course (April 30-May 4, 2001)
The SCALE KENO VI Criticality Course focuses
on KENO VI and the associated criticality analysis sequences in CSAS6.
KENO VI is the latest version of the KENO Monte Carlo criticality safety
code. KENO VI contains a much larger set of geometrical bodies than KENO
V.a, including cuboids, cylinders, spheres, cones, dodecahedrons, elliptical
cylinders, ellipsoids, hoppers, parallelpipeds, planes, rhomboids, and
wedges. The flexibility of KENO VI is increased by allowing the following
features: intersecting geometry regions; hexagonal as well as cuboidal
arrays; regions, holes, arrays, and units rotated to any angle and truncated
to any position; and the use of an array boundary that intersects the array.
Users should be aware that the added geometry features in KENO VI can result
in significantly longer run times than KENO V.a. A KENO VI problem that
can be modeled in KENO V.a will typically run four times as long in KENO
VI as in KENO V.a. Thus the new version VI is not a replacement for the
existing version V.a, but an additional version for more complex geometries
that could not be modeled previously. Two-dimensional color plots of the
geometry model can be generated in KENO V.a, or the model may be viewed
using the KENO3D 3-D visualization tool.
SCALE KENO-Va Criticality Course (October 22-26, 2001)
The SCALE KENO V.a Criticality Course focuses
on KENO V.a and the associated criticality analysis sequences in CSAS.
KENO V.a is a widely used 3-D multigroup Monte Carlo criticality safety
analysis code that has been in use for approximately 15 years. 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
Implications for Radiation Measurement Science, Atmospheric and Biospheric Processes, and Health Effects from Worldwide Fallout, Apr. 4-5, 2001, Arlington, VA, sponsored by the National Council on Radiation Protection and Measurements. Contact: William M. Beckner (tel 301-657-2652, fax 301-907-8768, url www.ncrp.com).
33rd National Conference on Radiation Control, Apr. 29-May 2, 2001, Anchorage, AK, sponsored by Conference of Radiation Control Program Directors, Inc. (tel 502-227-4543, fax 502-227-7862, email firstname.lastname@example.org, url www.crcpd.org)
Ninth International High-Level Radioactive Waste Management Conference, Apr. 29-May 3, 2001, Las Vegas, NV, sponsored by ANS and others. Contact: Daniel Bullen, IHLRWM General Chair, (tel 515-294-6000, fax 515-294-3261, email email@example.com).
Radiation Transport Calculations Using the EGS Monte Carlo System, Apr. 30 - May 3, 2001, 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, e-mail firstname.lastname@example.org, url www.irs.inms.nrc.ca/inms/irs/papers/egsnrc/brochure.html).
The ANSWERS Software Service Reactor Physics, Radiation Shielding and Nuclear Criticality Annual Seminar, May 15-17, 2001, Bournemouth, Dorset, United Kingdom, sponsored by the AEA Technology. Contact: Simon Aplin (tel + 44 (0) 1305 203634, fax +44 (0) 1305 202746, email email@example.com url www.aeat.co.uk/answers).
MONK Nuclear Criticality Introductory Workshop (Includes code trial), June 4-8, 2001, University of New Mexico, Albuquerque. Contact: Simon Aplin, AEA Technology, ANSWERS Software Service. (tel +44 (0) 1305 203634, fax +44 (0) 1305 202746, email firstname.lastname@example.org, url www.aeat.co.uk/answers).
ANS Annual Meeting, June 17-21, 2001, Milwaukee, WI (url www.ans.org).
Monte Carlo Analysis, Aug. 13-17, 2001, Knoxville, TN, a short course by the University of Tennessee. Contact: Kristin England, Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996 (tel 865-974-5048, email email@example.com , url http://www.engr.utk.edu/dept/nuclear/TIW.html).
Nuclear Criticality Safety, Aug. 13-17, 2001, Knoxville, TN, a short course by the University of Tennessee. Contact: Kristin England, Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996 (tel 865-974-5048, email firstname.lastname@example.org, url http://www.engr.utk.edu/dept/nuclear/TIW.html).
M&C 2001 Annual Meeting - Special Session: Variance Reduction for Monte Carlo Criticality Simulations, Sept. 9-13, 2001, Salt Lake City, UT. Contact: Dr. Bojan Petrovic, (tel 412-256-1295, fax 412-256-2444, email PetrovB@westinghouse.com, url http://www.srv.net/~ians/MC2001).
Actinides Conference, Nov. 4-9, 2001,
Hayama, Japan. Contact: Dr. T. Ogawa, Secretary for Actinides-2001 (fax
+81-29-282-5922, email email@example.com,
Ann. Nucl. Energy, 28, 519-530 . . . A Pulsed Measurement of the Effective Thermal Neutron Absorption Cross-Section of a Heterogeneous Medium. . . . Drozdowicz, K.; Gabanska, B.; Igielski, A.; Krynicka, E.; Woznicka, U. . . . April 2001 . . . The Henryk Niewodniczanski Institute of Nuclear hysics, Krakow, Poland.
Ann. Nucl. Energy, 28, 531-552 . . . Neutrons and Antimony: Measurement, Interpretation and Evaluation. . . . Smith, A.B.; Fessler, A. . . . April 2001 . . . Argonne National Laboratory, Argonne, IL; University of Arizona, Tucson, AZ.
Ann. Nucl. Energy, 28, 585-616 . . . A Multi-region Boundary Element Method for Multigroup Neutron Diffusion Calculations. . . . Ozgener, H.A.; Ozgener, B. . . . April 2001 . . . Istanbul Technical University, Istanbul, Turkey.
Ann. Nucl. Energy, 28, 617-618 . . . Nuclear Reactor Theory in Canada 1943-1946. . . . Williams, P.M.M.R. . . . May 2001.
Ann. Nucl. Energy, 28, 619-657 . . . Boundary Conditions at Thin Absorbing Shells and Plates. I. . . . Wallace, P.R. . . . May 2001 . . . National Research Council of Canada, Montreal, Canada.
Ann. Nucl. Energy, 28, 659-688 . . . Theoretical Derivation of the Interaction Effects with an Eccentric Cell Model and Void Fraction Propagation in Two-phase Flow. . . . Espinosa-Paredes, G. . . . May 2001 . . . Universidad Autonoma Metropolitana-Iztapalapa, Mexico D.F., Mexico.
Ann. Nucl. Energy, 28, 689-700 . . . Improved Los Alamos Model Applied to the Neutron Induced Fission of 239Pu and 240Pu and to the Spontaneous Fission of Pu Isotopes. . . . Vladuca, G.; Tudora, A. . . . May 2001 . . . Bucharest University, Bucharest-Magurele, Romania.
Ann. Nucl. Energy, 28, 701-713 . . . Validation of an MCNP4B Whole-reactor Model for LWR-PROTEUS Using ENDF/B-V, ENDF/B-VI and JEF-2.2 Cross-section Libraries. . . . Joneja, O.P.; Plaschy, M.; Jatuff, F.; Luthi, A.; Murphy, M.; Seiler, R.; Chawla, R. . . . May 2001 . . . Paul Scherrer Institute, Villigen PSI, Switzerland; Swiss Federal Institute of Technology, Lausanne, Switzerland.
Ann. Nucl. Energy, 28, 715-721 . . . Spherical Harmonics Moments of Neutron Angular Flux for Spherically Symmetric Systems. . . . Sharma, A. . . . May 2001 . . . Bhabha Atomic Research Centre, Mumbai, India.
Nucl. Sci. Eng., 137, 117-145 . . . Analysis of Correlated Coupling of Monte Carlo Forward and Adjoint Histories. . . . Ueki, T.; Hoogenboom, J.E.; Kloosterman, J.L. . . . February 2001 . . . Delft University of Technology, JB Delft, The Netherlands.
Nucl. Sci. Eng., 137, 146-155 . . . New Photon Biasing Schemes for the "Once-More-Collided-Flux-Estimator" Method. . . . Authier, N.; Both, J.P.; Nimal, J.C. . . . February 2001 . . . Centre d'Etudes Nucleaires Saclay, Gif-sur-Yvette, France.
Nucl. Sci. Eng., 137, 156-172 . . . An Application of Linear Superposition to Estimating Lattice-Physics Parameters. . . . Zheng, J.; Guo, T.; Maldonado, G.I. . . . February 2001 . . . Iowa State University, Ames, IA.
Nucl. Sci. Eng., 137, 173-182 . . . Parallel Implementation of the Integral Transport Equation-based Radiography Simulation Code. . . . Inanc, F.; Vasiliu, B.; Turner, D. . . . February 2001 . . . Iowa State University, Ames, IA.
Nucl. Sci. Eng., 137, 183-193 . . . Neutron Capture Cross Section of 232Th. . . . Wisshak, K.; Voss, F.; Kappeler, F. . . . February 2001 . . . Institut fur Kernphysik, Karlsruhe, Germany.
Nucl. Sci. Eng., 137, 194-205 . . . Validation of the Characteristic Function Model for the Unresolved Resonance Region. . . . Koyumdjieva, N.; Janeva, N.; Volev, K. . . . February 2001 . . . Bulgarian Academy of Sciences, Sofia, Bulgaria.
Nucl. Sci. Eng., 137, 215-225 . . . New Photon Exposure Buildup Factors. . . . Chibani, O. . . . February 2001 . . . Radiation Detection Laboratory, Alger-gare, Algeria.
Nucl. Technol., 133, 141-152 . . . Development of a Simulation Model and Safety Evaluation for a Depressurization Accident Without Reactor Scram in an Advanced HTGR. . . . Nakagawa, S.; Saikusa, A.; Kunitomi, K. . . . February 2001 . . . JAERI, Ibaraki-ken, Japan.
Nucl. Technol., 133, 158-168 . . . Pluton: A Three-group Model for the Radial Distribution of Plutonium, Burnup, and Power Profiles in Highly Irradiated LWR Fuel Rods. . . . Lemehov, S.; Nakamura, J.; Suzuki, M. . . . February 2001 . . . JAERI, Ibaraki-ken, Japan.
Nucl. Technol., 133, 169-186 . . . Multidimensional TMI-1 Main-Steam-Line-Break Analysis Methodology Using Trac-PF/NEM. . . . Ivanov, K.N.; Beam, T.M.; Baratta, A.J.; Irani, A.; Trikouros, N.G. . . . February 2001 . . . Pennsylvania State University, University Park, PA; GPU Nuclear, Inc., Parsippany, NJ.
Nucl. Technol., 133, 187-193 . . . Assessment of the Athena Code for Calculating the Void Fraction of a Lead-Bismuth/Steam Mixture in Vertical Upflow. . . . Davis, C.B. . . . February 2001 . . . Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID.
Nucl. Technol., 133, 229-241 . . . Transmutation of Elemental Cesium by a Fusion Neutron Source. . . . Saito, M.; Apse, V.A.; Artisyuk, V.V.; Chmelev, A.N. . . . February 2001 . . . Tokyo Institute of Technology, Tokyo, Japan; Moscow Engineering Physics Institute, Moscow, Russia.
Nucl. Technol., 133, 242-252 . . . Concepts in Waste Management: Cerium-promoted Dissolution of Refractory Actinide Oxides. . . . Tedder, D.W.; Finney, B.C. . . . February 2001 . . . Georgia Institute of Technology, Atlanta, GA; Oak Ridge National Laboratory, Oak Ridge, TN.
Prog. Nucl. Energy, 37, 11-18 . . . Global Electrification and Nuclear Power: Toward Sustainable Growth in the New Millennium. . . . Kim, J.H.; Starr, C. . . . 2000 . . . EPRI, Palo Alto, CA.
Prog. Nucl. Energy, 37, 19-24 . . . Role of Nuclear Energy for Sustainable Development. . . . Mourogov, V.M. . . . 2000 . . . International Atomic Energy Agency, Vienna, Austria.
Prog. Nucl. Energy, 37, 25-30 . . . Nuclear Energy Strategy in the Environment of Utility Business Deregulation. . . . Minematsu, A. . . . 2000 . . . Tokyo Electric Power Company, Tokyo, Japan.
Prog. Nucl. Energy, 37, 31-35 . . . Comparative Health Risk Assessment of Coal Power and Nuclear Power in China. . . . Li Hong; Fang Dong . . . 2000 . . . Institute of Nuclear Energy Technology, Tsinghua University, Beijing, China.
Prog. Nucl. Energy, 37, 37-40 . . . Environmentally Friendly Methods of Water Disinfection: The Chemistry of Alternative Disinfectants. . . . Gordon, G.; Bubnis, B. . . . 2000 . . . Miami University, Oxford, OH.
Prog. Nucl. Energy, 37, 55-58 . . . The History and the Prospects of Japanese Nuclear Power Development Program. . . . Tsujikura, Y. . . . 2000 . . . Kansai Electric Power Co., Inc., Osaka, Japan.
Prog. Nucl. Energy, 37, 59-64 . . . SPWR Potential Features to Environment. . . . Tabata, H.; Yoshimura, M. . . . 2001 . . . Japan Atomic Power Company, Tokyo, Japan.
Prog. Nucl. Energy, 37, 65-70 . . . Regulatory Policies and the Future of Nuclear Power. . . . Marcus, G.H. . . . 2000 . . . U.S. Department of Energy, Washington, DC.
Prog. Nucl. Energy, 37, 71-76 . . .Non-proliferation Criteria for Nuclear Fuel Cycle Options. . . . Kiriyama, E.; Pickett, S. . . . 2000 . . . University of Tokyo, Tokyo, Japan.
Prog. Nucl. Energy, 37, 81-87 . . . The Role of Nuclear Power in the Sustainable Energy Future of Korea. . . . Lim, C.Y.; Moon, K.H.; Lee, B.W. . . . 2001 . . . Korea Atomic Energy Research Institute, Taejon, Korea.
Prog. Nucl. Energy, 37, 89-94 . . . Nuclear Power Under the Clean Development Mechanism. . . . Ikemoto, I.; Kanda, K. . . . 2000 . . . Kyoto University, Kyoto, Japan.
Prog. Nucl. Energy, 37, 95-100 . . . Roles of Nuclear Energy in Japan's Future Energy Systems. . . . Sato, O.; Shimoda, M.; Tatematsu, K.; Takokoro, Y. . . . 2000 . . . Japan Atomic Energy Research Institute, Ibaraki-ken, Japan.
Prog. Nucl. Energy, 37, 101-106 . . . Long Term Nuclear Power Role Under CO2 Emission Constraint. . . . Kurosawa, A. . . . 2000 . . . The Institute of Applied Energy, Tokyo, Japan.
Prog. Nucl. Energy, 37, 107-111 . . . Clean Development Mechanism and Nuclear Energy in China. . . . Fang Dong, Li Hong . . . 2000 . . . Tsinghua University, Beijing, China.
Prog. Nucl. Energy, 37, 119-124 . . . Design Study of the Demonstration FBR in Japan. . . . Inagaki, T.; Ohba, K.; Tazawa, H.; Murakami, T. . . . 2000 . . . The Japan Atomic Power Company, Tokyo, Japan.
Prog. Nucl. Energy, 37, 125-130 . . . Scenario Study on FBR Cycle Deployment. . . . Ono, K.; Hirao, K.; Ikegami, T. . . . 2000 . . . Japan Nuclear Cycle Development Institute, Ibaraki-ken, Japan.
Prog. Nucl. Energy, 37, 131-136 . . . A Conceptual Design Study on Innovative FBR. . . . Kasai, S.; Kubota, K.; Hayafune, H.; Ichimiya, M. . . . 2000 . . . Japan Nuclear Cycle Development Institute, Ibaraki-ken, Japan.
Prog. Nucl. Energy, 37, 137-144 . . . What is the Potential Use of Thorium in the Future Energy Production Technology? . . . Unak, T. . . . 2000 . . . Ege University, Izmir, Turkey.
Prog. Nucl. Energy, 37, 145-150 . . . A New Concept for the Nuclear Fuel Recycle System: Application of the Fluoride Volatility Reprocessing. . . . Kamoshida, M.; Kawamura, F.; Sasahira, A.; Fukasawa, T.; Sawa, T.; Yamashita, J. . . . 2000 . . . Power & Industrial Systems R&D Laboratory, Hitachi, Ltd., Ibaraki-ken, Japan.
Prog. Nucl. Energy, 37, 151-156 . . . Parc Process for an Advanced Purex Process. . . . Uchiyama, G.; Mineo, H.; Hotoku, S. Asakura, T.; Kamei, K.; Watanabe, M.; Nakano, Y.; Kimura . . . 2000 . . . JAERI, Ibaraki-ken, Japan.
Prog. Nucl. Energy, 37, 157-162 . . . Characteristics of Fuel Melting and Relocation in Metallic-Fueled Fast Reactor Core and Its Feasibility for Eliminating Recriticality. . . . Sawada, T.; Ninokata, H.; Taneichi, H.; Endo, H. . . . 2000 . . . Tokyo Institute of Technology, Tokyo, Japan; Nuclear Fuel Industries, Ltd., Tokyo, Japan; Toshiba Corporation, Yokohama, Japan.
Prog. Nucl. Energy, 37, 163-168 . . . High Level Radio-Active Wastes Reduction Through Fast Reactor. . . . Ikeda, K.; Kawakita, T.; Ohkubo, Y. . . . 2000 . . . Mitsubishi Heavy Industries, Ltd., Yokohama, Japan.
Prog. Nucl. Energy, 37, 169-175 . . . An Application of Metal Fuel Cycle Technology Toward Self-Consistent Nuclear Energy System (SCNES) Concept. . . . Fujita, R.; Yamaoka, M.; Kawashima, M.; Saito, M. . . . 2000 . . . Toshiba Corporation, Kawasaki, Japan; Tokyo Institute of Technology, Tokyo, Japan.
Prog. Nucl. Energy, 37, 177-185 . . . Feasibility Study of Large MOX Fueled FBR Core Aimed at the Self-Consistent Nuclear Energy System. . . . Fujimura, K.; Sanda, T.; Mayumi, M.; Moro, S.; Saito, M.; Sekimoto, H. . . . 2000 . . . Hitachi, Ltd., Power & Industry Systems, Ibaraki, Japan; The Institute of Applied Energy, Tokyo, Japan; Tokyo Institute of Technology, Tokyo, Japan.
Prog. Nucl. Energy, 37, 187-195 . . . Western and Asian Light Water Reactors at the Millennium Threshold. . . . Gavrilas, M.; Hejzlar, P. . . . 2000 . . . University of Maryland, College Park, MD; Czech Technical University, Prague, Czech Republic.
Prog. Nucl. Energy, 37, 197-204 . . . Subchannel Analysis of a Fast Reactor Cooled by Supercritical Light Water. . . . Mukohara, T.; Koshizuka, S.; Oka, Y. . . . 2000 . . . University of Tokyo, Ibaraki, Japan.
Prog. Nucl. Energy, 37, 205-210 . . . Multi-Fluid Multi-Phase Subchannel Analysis of Subassembly Accidents of LMFRS. . . . Kasahara, F.; Ninokata, H. . . . 2000 . . . Tokyo Institute of Technology, Tokyo, Japan.
Prog. Nucl. Energy, 37, 211-216 . . . Natural Circulation Capability of PB-BI Cooled Fast Reactor: PEACER. . . . Chang, J-E.; Suh, K.Y.; Hwang, I.S. . . . 2000 . . . Seoul National University, Seoul, Korea.
Prog. Nucl. Energy, 37, 217-222 . . . The Concept of Proliferation-Resistant, Environment-Friendly, Accident-Tolerant, Continual and Economical Reactor (PEACER). . . . Hwang, I.S.; Jeong, S.H.; Park, B.G.; Yang, W.S.; Suh, K.Y.; Kim, C.H. . . . 2000 . . . Seoul National University, Seoul, Republic of Korea; Chosun University, Kwang-ju, Republic of Korea.
Prog. Nucl. Energy, 37, 223-228 . . . Neutronic Potential of Water Cooled Reactor with Actinide Closed Fuel Cycle. . . . Takaki, N. . . . 2000 . . . The Japan Atomic Power Company, Ibaraki, Japan.
Prog. Nucl. Energy, 37, 229-234 . . . Minor Actinides Incineration by Loading Moderated Targets in Fast Reactor. . . . Takeda, T.; Sato, D.; Yamamoto, T.; Hongchun, W. . . . 2000 . . . Osaka University, Osaka, Japan.
Prog. Nucl. Energy, 37, 235-240 . . . On the Main Objectives of Transmutation Cycles for Long-Lived Fission Products and Minor Actinides. . . . Shmelev, A.; Apse, V.; Koulikov, G. . . . 2000 . . . Moscow Engineering Physics Institute, Moscow, Russia.
Prog. Nucl. Energy, 37, 241-246 . . . Equilibrium Characteristics of Typical Fuel Cycles of PWR. . . . Waris, A.; Sekimoto, H. . . . 2000 . . . Tokyo Institute of Technology, Tokyo, Japan.
Prog. Nucl. Energy, 37, 253-258 . . . Desirability of Small Reactors, HTGR in Particular. . . . Tsuchie, Y. . . . 2000 . . . The Japan Atomic Power Co., Tokyo, Japan.
Prog. Nucl. Energy, 37, 259-263 . . . A Very Small LWR Installed in the Underground in the City. . . . Ochiai, M-A. . . . 2000 . . . Japan Atomic Energy Research Institute, Ibaraki-ken, Japan.
Prog. Nucl. Energy, 37, 265-270 . . . Carem Project: Innovative Small PWR. . . . Fukami, M.V.I.; Santecchia, A. . . . 2000 . . . Comision Nacional de Energia Atomica, Capital Federal, Argentina; INVAP, SE, Rio Negro, Argentina.
Prog. Nucl. Energy, 37, 271-276 . . . Simple and Safe Deep Pool Reactor for Low-Temperature Heat Supply. . . . Jiafu Tian . . . 2000 . . . Tsinghua University, Beijing, China.
Prog. Nucl. Energy, 37, 277-282 . . . Conceptual Design on Multi-Purpose Heat Reactor "Nuclear Heat Generator." . . . Uchiyama, Y.; Ikemoto, I.; Shimamura, K.; Sasaki, M. . . . 2000 . . . University of Tsukuba, Ibaraki, Japan; Central Research Institute of Electric Power Industry, Tokyo, Japan; Mitsubishi Heavy Industries, Ltd., Yokohama, Japan.
Prog. Nucl. Energy, 37, 283-290 . . . A Design Study on MOX-Fueled Small Fast Reactors for Standardization of a Small Fast Nuclear Reactor System. . . . Uto, N.; Hayafune, H.; Wakabayashi, T. . . . 2000 . . . Japan Nuclear Cycle Development Institute, Ibaraki, Japan.
Prog. Nucl. Energy, 37, 291-298 . . . A Concept of the Multipurpose Liquid Metallic-Fueled Fast Reactor System (MPFR). . . . Endo, H.; Netchaev, A.; Yoshimura, K.; Arie, K.; Yamadate, M.; Sawada, T.; Ninokata, H. . . . 2000 . . . Toshiba Corporation, Yokohama, Japan; Tokyo Institute of Technology, Tokyo, Japan; Kawasaki Heavy Industry, Ltd.; Tokyo, Japan; Hitachi Engineering, Co., Ltd., Ibaraki-ken, Japan.
Prog. Nucl. Energy, 37, 299-306 . . . Long Life Multipurpose Small Size Fast Reactor with Liquid Metallic-Fueled Core. . . . Netchaev, A.; Saqwada, T.; Ninokata, H.; Endo, H. . . . 2000 . . . Tokyo Institute of Technology, Tokyo, Japan; Toshiba Corporation, Yokohama, Japan.
Prog. Nucl. Energy, 37, 307-312 . . . Modular High Temperature Reactor (Modular HTR) Contributing the Global Environment Protection. . . . Ohashi, K.; Okamoto, F.; Hayakawa, H. . . . 2000 . . . Fuji Electric Co., Ltd., Kawasaki-city, Japan.
Prog. Nucl. Energy, 37, 313-319 . . . Galllium-Cooled Liquid Metallic-Fueled Fast Reactor. . . . Sawada, T.; Netchaev, A.; Ninokata, H.; Endo, H. . . . 2000 . . . Tokyo Institute of Technology, Tokyo, Japan; Toshiba, Corporation, Yokohama, Japan.
Prog. Nucl. Energy, 37, 321-326 . . . Design Study on an Accelerator-Based Facility for BNCT and Low Energy Neutron Source. . . . Yokobori, H.; Sasaki, M.; Yamanaka, T. . . . 2000 . . . Advanced Reactor Technology Co. Ltd., Tokyo, Japan; Mitsubishi Heavy Industries, Ltd., Yokohama-shi, Japan.
Prog. Nucl. Energy, 37, 327-332 . . . Neutron Beam Design for Both Medical Neutron Capture Therapy and Industrial Neutron Radiography for Triga Rreactor. . . . Matsumoto, T. . . . 2000 . . . Atomic Energy Research Laboratory, Kawasaki-shi, Japan.
Prog. Nucl. Energy, 37, 333-337 . . . Recent Advances in Medical Radionuclide Production and Future Perspective of Compact Medical Cyclotrons. . . . Unak, T. . . . 2000 . . . Ege University, Izmir, Turkey.
Prog. Nucl. Energy, 37, 339-344 . . . Accelerator-Driven System for Transmutation of High-Level Waste. . . . Tsujimoto, K.; Sasa, T.; Nishihara, K.; Takizuka, T.; Tatkano, H. . . . 2000 . . . Japan Atomic Energy Research Institute, Ibaraki, Japan.
Prog. Nucl. Energy, 37, 345-350 . . . Transmutation Characteristics of Problematic Radionuclides in Spallation and Fusion Neutron Source. . . . Artisyuk, V.; Saito, M.; Shmelev, A. . . . 2000 . . . Tokyo Institute of Technology, Tokyo, Japan.
Prog. Nucl. Energy, 37, 351-356 . . . Data Base for Radiation Damage Analysis of Advanced Transmutors. . . . Korovin, Y.; Stankovsky, A.; Konobeyev, A.; Pereslavtsev, P.; Saito, M.; Artisyuk, V. . . . 2000 . . . Obninsk Institute of Nuclear Power Engineering, Kaluga Region, Russia; Tokyo Institute of Technology, Tokyo, Japan.
Prog. Nucl. Energy, 37, 357-362 . . . Accelerator Driven Subcritical System as a Future Neutron Source in Kyoto University Research Reactor Institute (KURRI) - Basic Study on Neutron Multiplication in the Accelerator Driven Subcritical Reactor . . . Shiroya, S.; Unesaki, H.; Kawase, Y.; Moriyama, H.; Inoue, M. . . . 2000 . . . Kyoto University, Osaka, Japan.
Prog. Nucl. Energy, 37, 363-369 . . . The Role of the Accelerator in Energy: (Recent Development of an Accelerator-Driven Systems (ADS)). . . . Takahashi, H. . . . 2000 . . . Brookhaven National Laboratory, Upton, NY.
Prog. Nucl. Energy, 37, 371-376 . . . Transmutation of Long-Lived Radioactive Waste Based on Double-Strata Concept. . . . Takano, H.; Nishihara, K.; Tsujimoto, K.; Sasa, T.; Oigawa, H.; Takizuka, T. . . . 2000 . . . Japan Atomic Energy Research Institute, Ibaraki-ken, Japan.
Prog. Nucl. Energy, 37, 377-382 . . . Radiotoxicity Hazard of U-Free PuO2+ZrO2 and PuO2+ThO2 Spent Fuels in LWR. . . . Shelley, A.; Akie, H.; Takano, H.; Sekimoto, H. . . . 2000 . . . Tokyo Institute of Technology, Tokyo, Japan; JAERI, Ibaraki-ken, Japan.
Prog. Nucl. Energy, 37, 383-386 . . . Radioactive Releases from Nuclear Waste Repository in the Tropical Climate Environment. . . . Imardjoko, Y.U. . . . 2000 . . . Gadjah Mada University, Yogyakarta, Indonesia.
Prog. Nucl. Energy, 37, 387-392 . . . Evaluation of Recycle P&T Treatment by Using BWR to Perform Geologic Disposal. . . . Kitamoto, A.; Setiawan, M.B.; Taniguchi, A. . . . 2000 . . . Tokyo Institute of Technology, Tokyo, Japan.
Prog. Nucl. Energy, 37, 393-397 . . . Leaching Behavior of Boric Acid and Cobalt from Paraffin Waste Forms. . . . Kim, J.Y.; Chung, C.H. . . . 2000 . . . Seoul National University, Seoul, Korea.
Prog. Nucl. Energy, 37, 399-404 . . . Structure and Kinetic Studies of U(VI)-Benzamidoxime Complex in Non-Aqueous Solutions by 1H- and 13C-NMR. . . . Kim, S.Y.; Harada, M.; Tomiyasu, H.; Ikeda, Y.; Park, Y.Y. . . . 2000 . . . Tokyo Institute of Technology, Tokyo, Japan.
Prog. Nucl. Energy, 37, 405-410 . . . Low Exergy Reactor for Decentralized Energy Utilization. . . . Kato, Y. . . . 2000 . . . Tokyo Institute of Technology, Tokyo, Japan.
Prog. Nucl. Energy, 38, 81-105 . . . The Application of Gas-Cooled Reactor Technologies to the Transmutation of Nuclear Waste. . . . Baxter, A.; Rodriguez, C. . . . 2001 . . . General Atomics, Los Alamos, NM.
Prog. Nucl. Energy, 38, 107-134 . . . Review of Research and Development of Accelerator-Driven System in Japan for Transmutation of Long-Lived Nuclides. . . . Mukaiyama, T.; Takizuka, T.; Mizumoto, M.; Ikeda, Y.; Ogawa, T.; Hasegawa, A.; Takada, H.; T . . . 2001 . . . JAERI, Ibaraki-ken, Japan.
Prog. Nucl. Energy, 38, 135-151 . . . Review of the European Project - Impact of Accelerator-Based Technologies on Nuclear Fission Safety (IABAT) . . . Gudowski, W.; Arzhanov, V.; Broeders, C.; Broeders, I.; Cetnar, J.; Cummings, R.; Ericsson, M.; Fogelberg, B.; Gaudard, C.; Koning, A.; Landeyro, P.; Magill, I.; Pazsit, P.; Peerani, P.; Phlippen, P.; Piontek, M.; Ramstrom, E.; Ravetto, P.; Ritter, G.; Shubin, Y.; Soubiale, S.; Toccoli, C.; Valade, M.; Wallenius, J.; Youinou, G. . . . 2001 . . . Kungliga Tekniska Hogskolan, Stockholm, Sweden; Commissariat a l'Energie Atomique CEA/CE, Saint Paul Lez Durance, France; Nuclear Research and Consultancy Group, Petten, The Netherlands; Forschungszentrum Juelich, Juelich, Germany; Politecnico di Torino, Torino, Italy; Ente per le Nuove Tenologie, l'Energia e l'Ambiente, Santa Maria Di Galeria, Italy; Forschungszentrum Karlsruhe, Karlsruhe, Germany; European Institute for Transuranium Elements, Karlsruhe, Germany; AEA Technology, Oxon, United Kingdom; University of Uppsala, Nykoping, Sweden; Chalmers Tekniska Hogskolan, Goteborg, Sweden; Paul Scherrer Institute, Villigen PSI, Switzerland; Academy of Mining and Metallurgy, Krakow, Poland; Institute of Physics and Power Engineering, Obninsk, Russia.
Prog. Nucl. Energy, 37, 153-166 . . . An Accelerator-Driven System for the Destruction of Nuclear Waste. . . . Revol, J-P. . . . 2001 . . . CERN, Geneva, Switzerland.
Prog. Nucl. Energy, 38, 167-178 . . . Review and Proposals About the Role of Accelerator Driven Systems Nuclear Power. . . . Salvatores, M.; Slessarev, I.; Berthou, V. . . . 2001 . . . Centre d'Etudes Atomiques, Saint Paul Lez Durance, France.
Prog. Nucl. Energy, 38, 179-219 . . . Nuclear Data for Accelerator-Driven Systems. . . . Chadwick, M.B.; Hughes, H.G.; Little, R.C.; Pitcher, E.J.; Young, P.G. . . . 2001 . . . Los Alamos National Laboratory, Los Alamos, NM.
KFK Proceedings 98-16; JHF-98-7 . . . Proceedings of JHF Symposium on Neutronics and Radiation Shielding for Spallation Neutron Source. . . . Kawa, M. ed. . . . February 1999 . . . KEK, Tsukuba, Japan.
NUREG/CR-6701; ORNL/TM-2000/277 . . . Review of Technical Issues Related to Predicting Isotopic Compositions and Source Terms for High-burnup LWR Fuel. . . . Gauld, I.C.; Parks, C.V. . . . January 2001 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
NUREG/CR-6702; ORNL/TM-2000/72 . . . Limited Burnup Credit in Criticality Safety Analysis: A Comparison of ISG-8 and Current International Practice. . . . Gauld, I.C. . . . January 2001 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
Book . . . Geological Disposal of Radioactive Wastes and Natural Analogues. . . . Miller, W.; Alexander, R.; Chapman, N.; McKinley, I.; Smellie, J. . . . November 2000 . . . QuantiSci Ltd, Leicestershire, UK; Nagra, Switzerland; Conterra AB, Sweden.