Introductory classes are for people who have little or no experience
with MCNP. This class surveys the features of MCNP so the beginning user
will be introduced to the capabilities of the program, and will have hands-on
experience at running the code to solve simple 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.
The intermediate to advanced class will be held for people who have
used MCNP and want to extend their knowledge and understanding of the code
system.
The class will be based on MCNP5 and will cover the new capabilities
of version 5. Attendees may elect to receive the new package. If you have
previously received an older registered version of MCNP from RSICC, you may
request that the MCNP5 package be sent to you at no charge. If you have not
received an older version of MCNP from RSICC, you will be charged the applicable
transmittal fee.
he other capabilities of MCNP will also be covered, including basic
and advanced geometry, source definitions, tallies, data, variance reduction,
statistical analysis, criticality, plotting of geometry, and particle tracks,
neutron/photon/electron physics.
All classes provide interactive computer instruction. Time will be
available to discuss individual questions and problems with MCNP experts
or to pursue in more detail topics mentioned in the talks.
Please note that other classes are offered based on MCNP. The classes
mentioned here are the only ones that are taught by the people who develop
and write MCNP.
The Visual Editor is a powerful visualization tool that can be used
to rapidly create complex Monte Carlo N Particle (MCNP5) geometry models,
including lattices, universes, fills, and other geometrical transformations.
The Visual Editor can:
Display source points and collision points in the plot window.
The class combines 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 Windows 2000. Attendees are encouraged
to bring their own input files for viewing and modifying in the visual editor.
For a more detailed description of this course, click here.
Further information on this class can be located at: http://www.mcnpvised.com/train.html,
or by contacting Randy Schwarz (email randyschwarz@mcnpvised.com).
Lead Teachers: Drs. John Hendricks, Gregg McKinney, Laurie Waters
MCNPX is the LANL all-particle, all-energy (eV-TeV) Monte Carlo transport
code based on MCNP4C, LAHET, CEM, etc. MCNPX has been in active development
since 1995, sponsored by the particle accelerator community. It has now become
an accepted tool for a broad range of applications by nuclear engineers,
physicists, and scientists. The MCNPX development effort has expanded the
use of the Los Alamos tools to applications such as APT, waste transmutation,
accelerator shielding and health physics, particle beam cancer therapy, space
shielding and cosmic ray analysis, single event effects in semiconductors,
radiography, and more detailed analysis of the effects of light and heavy
ions in matter. In addition, the entire functionality of MCNP4C is retained.
New variance reduction and data analysis techniques, many adapted from high
energy accelerator methodologies, have also been added, such as the extensive
'mesh tally' capability which allows up to 3-d plotting of particle tracks,
fluence and fluence-derived quantities, energy deposition, next event estimator
generation contributions and particle sources.
The workshops include hands-on instruction, generally on PC Windows
machines. Subject to participant export approval for the MCNPX beta test
team, participants will be able to access the Fortran-90 version of MCNPX
2.4, the LA150 (150 MeV) cross-section data for over 40 isotopes for incident
neutrons and protons, and 12 for photonuclear interactions, and a notebook
of viewgraphs. Follow-up consultation for class participants will be provided.
Classes are taught by experienced MCNPX code developers and instructors.
More information on code versions and capabilities is available at MCNPX
Workshops web site http://mcnpxworkshops
.com.
PHYSOR 2004
The Chicago Section of the American Nuclear Society is pleased to announce
that it will host the PHYSOR-2004 Topical Meeting, April 25-29, 2004,
in Chicago, Illinois. The meeting is co-sponsored by the Reactor Physics
Division of the ANS, OECD Nuclear Energy Agency, European Nuclear Society,
Canadian Nuclear Society, and the Brazilian National Atomic Energy Commission.
The conference will be held at the Hyatt Regency in downtown Chicago.
The title for the meeting is "The Physics of Fuel Cycles and Advanced
Nuclear Systems: Global Developments." The technical program will cover more
than 15 topical focus areas. You are invited to visit the meeting website
at www.physor2004.anl.gov to obtain updated information and to download a
copy of the meeting announcement. Contact: Ray Klann, Technical Program Co-Chair,
at 630-252-4305 or klann@anl.gov.
Practical MCNP for the HP, Medical
Physicist, and Rad Engineer
DATES: June 7-11, 2004
FEE: $1,450 per person
PLACE: The MESA Complex, Room 130, University of New Mexico-Los Alamos
Campus
Monte Carlo type calculations are ideally suited to solving a variety
of problems in radiation protection and dosimetry. This course is aimed at
the health physicist, 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 an overview of the MCNP code and the
Monte Carlo method, 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. 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, and 4.5 CM points by
the American Board of Industrial Hygiene. The course is offered by the Health
Physics Measurements Group at the Los Alamos National Laboratory and is co-sponsored
by RSICC.
Registration is available online at: http://drambuie.lanl.gov/~esh4/mcnp.htm.
Make checks payable to the University of California (checks must be in U.S.
dollars on a U.S. bank) and mail together with name, address, and phone number
to: Los Alamos National Laboratory, Group HSR-4, MCNP Class, David Seagraves,
Mail Stop J573, Los Alamos, NM 87545.
Inquiries regarding registration and class space availability should
be made to David Seagraves, 505-667-4959, fax: 505-665-7686, e-mail: dseagraves@lanl.gov. Technical
questions may also be directed to Dick Olsher, 505-667-3364; e-mail: dick@lanl.gov.
Please note that this course is separate from and independent of the
courses being offered by the MCNP and MCNPX Teams at LANL.
Short Course on "Introduction to Monte
Carlo Treatment Planning"
Course Director: Charlie Ma, Ph.D. ; Course Coordinator: Jinsheng Li,
Ph.D.
Contact information: Tel 215-728-5665, Fax: 215-728-4789; Email: js_li@fccc.edu
Webpage: http://www.fccc.edu/clinical/radiation_oncology/monte_carlo_course.html
Venue: Radiation Oncology, FCCC, Philadelphia, PA
Date: April 8-10, 2004
The course registration fee is $1600, which covers the course materials,
two lunches, two dinners and refreshments. A set of software is free for
the attendee. Discounts for students are available. Hotel information is
available upon request.
The short course is designed to train future Monte Carlo RTP users
and researchers in the use of Monte Carlo treatment planning software. The
course will include didactic instruction and hands-on workshops. The course
is specially suited for previous EGS4 and OMEGA/BEAM course participants,
who want to expand their research into clinical RTP. A working knowledge
of a Unix-based system is expected to run the Monte Carlo RTP software.
Enrollment will be limited to 20 people to facilitate instruction at
the hands-on labs. So please register early. Registration will be strictly
on a first-come basis. Please contact Dr. Jinsheng Li, at js_li@fccc.edu or see the website: http://www.fccc.edu/clinical/radiation_oncology/
monte_carlo_course.html.
2005 Conferences
Monte Carlo 2005 Topical Meeting
Monte Carlo 2005 will be held April 17-21, 2005, (Sunday-Thursday).
The theme of the conference will be "The Monte Carlo Method: Versatility
Unbounded in A Dynamic Computing World".
The conference site is the Chattanooga Marriott and Convention Center
in Chattanooga, Tennessee. The conference will be hosted by the American
Nuclear Society (ANS) Oak Ridge/Knoxville Section, with ANS Radiation Protection
and Shielding Division (RPSD) as the sponsoring division and Mathematics
and Computations Division (MCD) as a co-sponsor. Co-sponsors will also include
Oak Ridge National Laboratory (ORNL), Radiation Safety Information Computational
Center (RSICC) and the Organization for Economic Cooperation and Development
(OECD) Nuclear Energy Agency Data Bank (NEADB).
The Monte Carlo method and its applications have been frequently addressed
at several major conferences and workshops organized in recent years in the
area of nuclear applications. Monte Carlo topics have included radiation
shielding, radiation physics, medical physics, and high energy physics. Significant
developments have taken place in computational and data issues, resulting
in state-of-the-art computer codes and tools. Monte Carlo 2005 is the next
in a series devoted to the topic, following Monte Carlo 2000 which was held
in Lisbon, Portugal in October 2000.
Conference topics will include: Methods Advancements (Physics) (proton
transport, neutron transport, gamma transport, electron transport, heavy
ion transport); Nuclear Data Advancements (proton transport, neutron transport,
gamma transport, electron transport, heavy ion transport); Mathematical and
Computational Advances (experiments & benchmarks, mathematical advances,
computational advances, visualization); Applications (reactor, medical, accelerator,
neutron science, dosimetry, shielding, fuel cycle, waste management, space
& aviation, fusion, criticality safety, non-nuclear applications).
The website is http://MonteCarlo2005.org.
Full papers are due September 10, 2004. For information contact Bernadette
Kirk (kirkbl@ornl.gov, 865-574-6176),
General Chair, or Jeff Johnson (johnsonjo@ornl.gov,
865-574-5262), Technical Chair.
CALENDAR
March 2004
MCNPX Intermediate Workshop, Mar. 8-12, 2004, Santa
Fe, NM. Contact: Bill Hamilton (tel 505-455-0312, email registrar@mcnpxworkshops. com,
url http://mcnpxworkshops.com).
Decontamination and Decommissioning Training Course,
Mar. 8-12, 2004, Las Vegas, NV. Contact: Linda Legerski (tel 603-252-4836,
fax 630-252-5287, email lindal@anl.gov,
url http://www.td.anl.gov/D&D/).
Visual Editor for MCNP, Mar.15-19, 2004, Richland,
WA. Contact: Randy Schwarz (email randyschwarz@ mcnpvised.com,
url http://www.mcnpvised.com/
train.html).
21st Zurich Short Courses on Modeling and Computation of Multiphase
Flows, Mar. 22-26, 2004, Zurich. Contact: Prof. G. Yadigaroglu
(tel + 41 1 632 46 15, fax + 41 1 632 11 66, e-mail yadi@ethz.ch, url http://www.lkt.mavt.ethz.ch/courses/
multiphase/Short-Course.html).
April 2004
PHYSOR 2004 Reactor Physics Topical Meeting, Apr. 25-29,
2004, Chicago, IL. Jointly sponsored by the Reactor Physics Division of the
ANS and the Nuclear Energy Agency of the OECD and others. Contact:
Ray Klann (tel 630-252-4305, email klann@anl.gov,
url http://www.physor2004.anl.gov/).
9th Workshop on Monte Carlo Simulation of Radiotherapy Treatment
Sources Using the BEAM Code System, Apr. 26-29, 2004, Ottawa,
Canada. Contact: Dave Rogers (tel 613-520-2600 x4374, fax 613-520-4061, email
drogers@physics.carleton.ca,
url www.physics.carleton.ca/~drogers/BEAM/course/brochure.html).
May 2004
Current Topics in Monte Carlo Treatment Planning,
May 3-5, 2004, McGill University, Montreal, Canada. Contacts: Jan Seutjens
and Frank Verhaegen (tel 514-934-8052, url http://mctp.medphys.mcgill.ca).
MCNPX Intermediate Workshop, May 3-7, 2004, Lisbon,
Portugal Contact: Bill Hamilton (tel 505-455-0312, email registrar@mcnpxworkshops.com,
url http://mcnpxworkshops.com for
details).
International Conference on Radiation Shielding (ICRS-10) and Topical
Mtg. on Radiation Protection & Shielding (RPS 2004), May
9-14, 2004, Funchal, Madeira Island (Portugal). Contact: Conference Secretariat
(email icrs-rps@itn.mces.pt, url
http://www.itn.mces.pt/ICRS-RPS).
5th Intl. Conference on Nuclear Option in Countries with Small
and Medium Electricity Grids, May 16-20, 2004., Dubrovnik, Croatia,
Contact Prof. Nenad Debrecin (tel +385- 1-6312-399, email hnd2004@fer.hr, url http://hnd.zvne.fer.hr/Dubrovnik2004).
June 2004
Practical MCNP for the HP, Medical Physicist, and Rad Engineer,
June 7-11, 2004, Univ. of New Mexico, Los Alamos Campus. Contact: David Seagraves,
(tel 505-667-4959, fax 505-665-7686, e-mail dseagraves@lanl.gov. Technical questions
may also be directed to Dick Olsher, 505-667-3364; e-mail dick@lanl.gov, url http://drambuie.lanl.gov/~esh4/mcnp.htm).
MCNPX Intermediate Workshop, June 14-18, 2004, Houston,
TX. Contact: Bill Hamilton (tel 505-455-0312, email registrar@mcnpxworkshops.com,
url http://mcnpxworkshops.com for
details).
July 2004
MCNPX Introductory Workshop, July 12-16, 2004, Santa
Fe, NM. Contact: Bill Hamilton (tel 505-455-0312, email registrar@mcnpxworkshops.com,
url http://mcnpxworkshops.com for
details).
September 2004
1st International Symposium on Radionuclide Therapy and Radiopharmaceutical
Dosimetry, Sept. 4-8, 2004, Helsinki, Finland. Contact: Michael
Lassmann or Val Lewington, (emails lassmann@ nuklearmedizin.uni-wuerzburg.de;
vjlewington@ hotmail.com).
16th American Nuclear Society Topical Meeting on the Technology
of Fusion Energy, Sept. 14-16, 2004, Madison, WI. (url http://fti.neep.wisc.edu/tofe).
International Conference on Nuclear Data for Science and Technology
"ND2004", Sept. 26-Oct. 1, 2004, Santa Fe, NM. (Contact: http://t16web.lanl.gov/nd2004/).
5th International Conference of Yugoslav Nuclear Society (YUNS)
- 2004, Sept. 27-30, 2004, Belgrade, Serbia & Montenegro.
Contact: Dr. Milan Pesic, (tel 381-11-245-82-22/ext. 681, email mpesic@vin.bg.ac.yu, url http://www.vin.bg.ac.yu/YUNS/index.htm).
October 2004
11th World Congress on Neutron Capture Therapy (ISNCT-11),
Oct. 11-15, 2004, Boston, MA. Contact: Robert G. Zamenhof (tel 617-636-1681,
fax 617-636-5867, email rzamenhof@tufts-nemc.org,
url http://meetingsandconferences.com/ISNCT-11/).
April 2005
Monte Carlo 2005 Topical Meeting, Apr. 17-21, 2005,
Chattanooga, TN. Contact: Bernadette Kirk (tel 865-574-6176, fax 865-241-4046,
email kirkbl@ornl.gov, url http://meetingsandconference.com
/MonteCarlo2005).
ACCESSION
OF NUCLEAR SYSTEMS LITERATURE
The nuclear systems literature (shielding, safety, materials) cited
below has been reviewed and placed in the RSICC Information Storage and Retrieval
Information System (SARIS), now searchable on the RSICC web server (http://www-rsicc.ornl.gov/SARIS.html).
We now include medical physics in addition to material science, radiation
dosimetry, radiation safety, reactor dynamics, reactor safeguards, risk assessment,
waste management, fuel cycle, fusion and plasmas, high energy particle transport,
and shielding. This early announcement is made as a service to the nuclear
sciences community. Copies of the literature are not distributed by RSICC.
They may generally be obtained from the author or from a documentation center
such as the National Technical Information Service (NTIS), Department of
Commerce, Springfield, Virginia 22161.
Ann. Nucl. Energy, 30, 1821-1828. . . Cross-Section
Measurements for the 97Mo (n,p) 97mNb Reaction at the Neutron Energies from
13.6 to 14.9 MeV. . . .Bostan, M. et al. . . . December 2003. . . Istanbul
University, Turkey; Cekmece Nuclear Research & Training Center, Istanbul,
Turkey.
Ann. Nucl. Energy, 30, 1829-1845. . . Introducing
the Migration Mode Method for the Solution of the Space and Energy Dependent
Diffusion Equation. . . .Dall-Osso, A. . . . December 2003. . . Framatome
ANP, Cedex, France.
Ann. Nucl. Energy, 30, 1847-1862. . . Measurements
of the (n,np+d) Activation Cross Sections with 13.4-14.9 MeV Neutrons Using
a Fusion Neutronics Source/JAERI. . . .Sakane, H. et al. . . . December
2003. . . Nagoya University, Japan; JAERI, Ibaraki-ken, Japan.
Ann. Nucl. Energy, 30, 1879-1898. . . Improved
Performances of the Fast Reactor Calculational System ERANOS-ERALIB1 Due
To Improved A Priori Nuclear Data and Consideration of Additional Specific
Integral Data. . . .Fort, E. et al. . . . December 2003. . . Commissariat
a l'Energie Atomique, St.-Paul-Lez-Durance, France; AEA Technology, Dorset,
UK; Electricite de France, Villeurbanne, France; Framatome, Lyon Cedex, France.
Ann. Nucl. Energy, 30, 1899-1903. . . Immobilization
of 137Cs and 60Co in Concrete Matrix. . . .Plecas, I. . . . December
2003. . . None listed.
Ann. Nucl. Energy, 30, 1905-1917. . . On
the Use of Silicon as Thermal Neutron Filter. . . .Adib, M. et al. .
. . December 2003. . . NRC, AEA, Cairo, Egypt; Ain Shames University, Cairo,
Egypt.
Ann. Nucl. Energy, 30, 1921. . . Erratum
to: An Application of the Wiener-Hopf Method to the One-Speed Flat-Flux Problem
in a Half-Space [Ann. Nucl. Energy, 30 (2003) 1333-1345]. . . .Cassell,
J.S. et al. . . . December 2003. . . London Metropolitan University, UK;
Imperial College of Science , London, UK.
Ann. Nucl. Energy, 31, 9-23. . . Proof
of the Formula for the Ideal Gas Scattering Kernel for Nuclides with Strongly
Energy Dependent Scattering Cross Sections. . . .Rothenstein, W. . .
. January 2004. . . Technion-Israel Institute of Technology, Haifa, Israel.
Ann. Nucl. Energy, 31, 25-42. . . Some
Aspects of Random Geometry and Absorption in Multiplying Systems and the
Pulsed Neutron Problem. . . .Williams, M.M.R. . . . January 2004. .
. Imperial College of Science, London, UK.
Ann. Nucl. Energy, 31, 43-53. . . Heuristic
Derivation of the Rossi-Alpha Formula for a Pulsed Neutron Source. .
. .Baeten, P, . . . January 2004. . . SCK-CEN, Mol, Belgium.
Ann. Nucl. Energy, 31, 55-69. . . The
Fuzzy Clearing Approach for a Niching Genetic Algorithm Applied to a Nuclear
Reactor Core Design Optimization Problem. . . .Sacco, W.F. et al. .
. . January 2004. . . Universidade Federal do Rio de Janeiro, Brazil; Comissao
Nacional de Energia Nuclear, Rio de Janeiro, Brazil.
Ann. Nucl. Energy, 31, 71-86. . . Analytic
Derivation of the Correction Factor for the Improved Coarse Mesh Method.
. . .Yamamoto, A. . . . January 2004. . . Nagoya University, Japan.
Ann. Nucl. Energy, 31, 87-96. . . Feasibility
Study of Iridium Production at ETRR-2. . . .Abou-Zaid, A.A. et al. .
. . January 2004. . . AEA, Cairo, Egypt.
Ann. Nucl. Energy, 31, 97-106. . . Experimental
Studies on Measurements of Mass Attenuation Coefficients of Boric Acid at
Different Concentration. . . .Icelli, O. et al. . . . January 2004.
. . Ataturk University, Erzincan, Turkey.
Ann. Nucl. Energy, 31, 107-115. . . Effects
Analysis Fuzzy Inference System in Nuclear Problems Using Approximate Reasoning.
. . .Guimaraes, A.C.F. et al. . . . January 2004. . . Instituto de Engenharia
Nuclear, Rio de Janeiro, Brazil.
Ann. Nucl. Energy, 31, 117-133. . . Theoretical
Derivation of the Interaction Effects with Expansion Effects to Bubbly Two-Phase
Flows. . . .Espinosa-Paredes, G. et al. . . . January 2004. . . Universidad
Autonoma Metropolitana-Iztapalapa, Mexico; Instituto Mexicano del Petroleo,
Mexico.
Ann. Nucl. Energy, 31, 135-149. . . Neutronics
and Thermal Effects of Graphite Foams in the Performance of Nuclear Energy
Systems. . . .Difilippo, F.C. . . . January 2004. . . Oak Ridge National
Laboratory, Oak Ridge, TN.
Ann. Nucl. Energy, 31, 151-161. . . BWR
Fuel Reloads Design Using a Tabu Search Technique. . . .Castillo, A.
et al. . . . January 2004. . . Instituto Nacional de Investigaciones Nucleares,
Edo. de Mexico, Mexico; Universidad Nacional Autonoma de Mexico, Mexico;
Instituto Politecnico Nacional, Mexico.
Ann. Nucl. Energy, 31, 163-172. . . Experimental
Investigation of Variance-To-Mean Formula for Periodic and Pulsed Neutron
Source. . . .Kitamura, Y. et al. . . . January 2004. . . Nagoya University,
Japan; Kyoto University, Osaka, Japan.
Ann. Nucl. Energy, 31, 173-196. . . The
Burnup Capabilities of the Deep Burn Modular Helium Reactor Analyzed by the
Monte Carlo Continuous Energy Code MCB. . . .Talamo, A. et al. . . .
January 2004. . . Royal Institute of Technology, Stockholm, Sweden; Los Alamos
National Laboratory, Los Alamos, New Mexico.
Ann. Nucl. Energy, 31, 197-212. . . Theoretical
and Experimental Investigations of Reactor Parameters in a U-233 Fueled Research
Reactor. . . .Mohapatra, D.K. et al. . . . January 2004. . . Indira
Gandhi Centre for Atomic Research, Kalpakkam, India.
Ann. Nucl. Energy, 31, 213-225. . . Transport-Burnup
Code Systems and Their Applications for IAEA ADS Benchmark. . . .Xiaofeng
Jiang et al. . . . January 2004. . . Xi'an Jiaotong University, Shaanxi,
China.
Ann. Nucl. Energy, 31, 231-253. . . Discrete
Formulation for Two-Dimensional Multigroup Neutron Diffusion Equations. .
. .Vosoughi, N. et al. . . . February 2004. . . Sharif University of Technology,
Tehran, Iran; Atomic Energy Organization of Iran, Tehran, Iran; University
of Trieste, Italy; Shahid Beheshti University, Tehran, Iran.
Ann. Nucl. Energy, 31, 255-275. . . Effects
of Dispersed Flow Interfacial Area/Shear Modeling and Node Size in the Core
on TRAC-BF1 Rod Surface Temperature (RST) Histories of Separate-Effect and
System Calculations. . . .Analytis, G. Th. . . . February 2004. . .
Paul Scherrer Institute, Villigen, Switzerland.
Ann. Nucl. Energy, 31, 277-301. . . Sensitivity
Analysis and Fuzzy Modelling for Passive Systems Reliability Assessment.
. . .Zio, E. et al. . . . February 2004. . . Polytechnic of Milan, Italy.
Ann. Nucl. Energy, 31, 303-309. . . A
PHWR With Slightly Enriched Uranium. About the First Core. . . .Notari,
C. . . . February 2004. . . AEC of Argentina, Buenos Aires, Argentina.
Ann. Nucl. Energy, 31, 311-322. . . Fuzzy
Inference System for Evaluating and Improving Nuclear Power Plant Operating
Performance. . . .Guimaraes, A.C.F. et al. . . . February 2004. . .
Instituto de Engenharia Nuclear, Rio de Janeiro, Brazil.
Ann. Nucl. Energy, 31, 323-329. . . Indications
of the Validity of the Liquid Drop Model for Spontaneous Fission Half-Lives.
. . .Ronen, Y. . . . February 2004. . . Ben-Gurion University of the
Negev, Beer-Sheva, Israel.
Ann. Nucl. Energy, 31, 331-341. . . Measurement
of the Syrian MNSR Delayed Neutron Fraction and Neutron Generation Time By
Noise Analysis. . . .Khamis, I. et al. . . . February 2004. . . Atomic
Energy Commission of Syria, Damascus, Syria.
Ann. Nucl. Energy, 31, 343-356. . . Development
of BWR Control Rods Pattern Design System Based on Fuzzy Logic and Knowledge.
. . .Francois, J-L. et al. . . . March 2004. . . Universidad Nacional
Autonoma de Mexico, Mor., Mexico.
Ann. Nucl. Energy, 31, 357-373. . . Liquid
Velocity in Upward and Downward Air-Water Flows. . . .Sun, X. et al.
. . . March 2004. . . Purdue University, West Lafayette, IN.
Ann. Nucl. Energy, 31, 375-397. . . Identification
Method of Stochastic Nonlinear Dynamics Using Dynamical Phase Analysis-Application
to Forsmark Data. . . .Watanabe, F. et al. . . . March 2004. . . Tepco
Systems Corp., Tokyo, Japan; University of Tsukuba, Ibaraki, Japan; Toshiba
Corp., Yokohama-City, Japan.
Ann. Nucl. Energy, 31, 399-411. . . Beam
Optimization: Improving Methodology. . . .Quinteiro, G.F. . . . March
2004. . . Comision Nacional de Energia Atomica, Buenos Aires, Argentina.
Ann. Nucl. Energy, 31, 413-429. . . A
Comparative Physics Study of Alternative Long-Term Strategies for Closure
of the Nuclear Fuel Cycle. . . .Cometto, M. et al. . . . March 2004.
. . Paul Scherrer Institute, Villigen, Switzerland; Swiss Federal Institute
of Technology, Lausanne, Switzerland; Huttenacherstrasse, Oberrohrdorf, Switzerland.
Ann. Nucl. Energy, 31, 431-457. . . Genetic
Algorithms and Artificial Neural Networks for Loading Pattern Optimisation
of Advanced Gas-Cooled Reactors. . . .Ziver, A.K. et al. . . . March
2004. . . Imperial College of Science, London, UK; British Energy Generation,
Ltd., Gloucester, UK.
Ann. Nucl. Energy, 31, 459-480. . . Minimizing
the Gamma Radiation Effects to Spent Fuel Pool Walls.' . . .Tippayakul,
C. et al. . . . March 2004. . . Penn. State University, PN; Exelon Corp.
USA.
Ann. Nucl. Energy, 31, 481-516. . . Probabilistic
Safety Analysis of a Greek Research Reactor. . . .Aneziris, O.N. et
al. . . . March 2004. . . National Center for Scientific Research, Aghia
Paraskevi, Greece.
Ann. Nucl. Energy, 31, 517-540. . . Development,
Assessment and Application of TRAC-BF1/v2001.2 for Beyond Design Basis BWR
LOCA Transients. . . .Analytis, G. Th. et al. . . . March 2004. . .
Paul Scherrer Institute, Villigen, Switzerland.
Ann. Nucl. Energy, 31, 541-576. . . Minimum
Critical Mass and Flat Flux in a 2-Group Model. . . .Lewins, J. . .
. March 2004. . . University of Cambridge, UK.
Ann. Nucl. Energy, 31, 577-582. . . The
Photon Attenuation Coefficients of Barite, Marble and Limra. . . .Akkurt,
I. et al. . . . March 2004. . . Suleyman Demirel University, Isparta, Turkey.
Nucl. Eng. & Design, 226, 83-96. . . Reference
Stress Based Fracture Mechanics Analysis for Circumferential Through-Wall
Cracked Pipes: Experimental Validation. . . .Kim, Y-J. et al. . . .
December 2003. . . Sungkyunkway University, Kyonggi-do, South Korea.
Nucl. Eng. & Design, 226, 97-105. . .
Friction and Wear of Inconel 690 and Inconel 600 for Steam Generator
Tube in Room Temperature Water. . . .Lim, M-K. et al. . . . December
2003. . . Sungkyunkwan University, Kyung-Gi-Do, South Korea.
Nucl. Eng. & Design, 226, 107-118. . .
The 3D Surface Crack-Front Constraints in Bimaterial Joints. . .
.Lee, H. . . . December 2003. . . Sogang University, Seoul, South Korea.
Nucl. Eng. & Design, 226, 119-125. . .
Dynamic Material Property Characterization by Using Split Hopkinson Pressure
Bar (SHPB) Technique. . . .Lee, O.S. et al. . . . December 2003. . .
InHa University, Incheon, South Korea.
Nucl. Eng. & Design, 226, 127-140. . .
The Effects of the Stainless Steel Cladding in Pressurized Thermal Shock
Evaluation. . . .Jang, C. et al. . . . December 2003. . . Korea Institute
of Nuclear Safety, Daejeon, South Korea; Korea Electric Power Research Institute,
Daejeon, South Korea.
Nucl. Eng. & Design, 226, 141-154. . .
Round Robin Analysis of Pressurized Thermal Shock for Reactor Pressure
Vessel. . . .Jhung, M.J. et al. . . . December 2003. . . Korea Institute
of Nuclear Safety, Daejeon, South Korea.
Nucl. Eng. & Design, 226, 155-164. . .
Numerical and Experimental Investigations into Life Assessment of Blade-Disc
Connections of Gas Turbines. . . .Issler, S. et al. . . . December 2003.
. . University of Stuttgart, Germany.
Nucl. Eng. & Design, 226, 165-182. . .
Risk-Based Inspection and Maintenance in Power and Process Plants in
Europe. . . . Jovanovic, A. . . . December 2003. . . MPA Stuttgart,
Germany.
Nucl. Eng. & Design, 226, 183-191. . .
Transient Analysis of Thick-Walled Piping Under Polynomial Thermal Loading.
. . .Segall, A.E. . . . December 2003. . . Penn. State University, University
Park, PA.
Nucl. Eng. & Design, 226, 193-204. . .
Crack Opening Displacement of a Through-Wall Crack in a Plate Subjected
to Bending Load. . . .Machida, H. et al. . . . December 2003. . . TEPCO
Systems Corp., Tokyo, Japan; Japan Nuclear Cycle Development Institute, Ibaraki,
Japan.
Nucl. Eng. & Design, 226, 221-230. . .
Multi-Damping Earthquake Design Spectra-Compatible Motion Histories.
. . .Choi, D-H. et al. . . . December 2003. . . Hanyang University, Seoul,
South Korea; Korea Power Engineering Co., Gyeonggi-do, South Korea.
Nucl. Eng. & Design, 226, 231-241. . .
Comparison of Pressure Vessel Integrity Analyses and Approaches for VVER
1000 and PWR Vessels for PTS Conditions. . . .Gulol, O.O. et al. . .
. December 2003. . . Turkish Atomic Energy Authority, Ankara, Turkey; Hacettepe
University, Ankara, Turkey.
Nucl. Eng. & Design, 226, 243-254. . .
Identification of Damping Mechanism of TRR-II Reactor Control Rod During
Free Fall Insertion. . . .Wang, S.K. et al. . . . December 2003. . .
I-Shou University, Kaohsiung, Taiwan; National Central University, Chung-Li,
Taiwan; Institute of Nuclear Energy Research, Lung-Tan, Taiwan.
Nucl. Eng. & Design, 226, 255-265. . .
Three-Dimensional Analysis of Flow Characteristics on the Reactor Vessel
Downcomer During the Late Reflood Phase of a Postulated LBLOCA. . .
.Kwon, T-S. et al. . . . December 2003. . . KAERI, Daejeon, South Korea.
Nucl. Eng. & Design, 226, 267-275. . .
Development of a Thermal-Hydraulic Analysis Code for Annular Fuel Assemblies.
. . .Han, K.H. et al. . . . December 2003. . . Korea Advanced Institute of
Science and Technology, Daejeon, South Korea.
Nucl. Eng. & Design, 226, 277-292. . .
One-Dimensional Critical Heat Flux Concerning Surface Orientation and
Gap Size Effects. . . .Kim, Y.H. et al. . . . December 2003. . . Seoul
National University, Seoul, South Korea.
Nucl. Eng. & Design, 226, 311-336. . .
The Analytic Hierarchy Process as a Systematic Approach to the Identification
of Important Parameters for the Reliability Assessment of Passive Systems.
. . .Zio, E. et al. . . . December 2003. . . Polytechnic of Milan, Milano,
Italy.
Nucl. Eng. & Design, 226, 337-349. . .
Improvement of HYCA3D Code and Experimental Verification in Rectangular
Geometry. . . .Choi, Y-S. et al. . . . December 2003. . . Seoul National
University, South Korea.
Nucl. Eng. & Design, 226, 351-373. . .
Cost and Performance Design Approach for GTHTR300 Power Conversion System.
. . .Yan, X. et al. . . . December 2003. . . JAERI, Ibaraki-ken, Japan; Mitsubishi
Heavy Industries, Japan.
Nucl. Eng. & Design, 226, 375-385. . .
The Removal of the Pertechnetate Ion and Actinides from Radioactive Waste
Streams at Hanford, Washington, USA and Sellafield, Cumbria, UK: The Role
of Iron-Sulfide-Containing Adsorbent Materials. . . .Watson, J.H.P.
et al. . . . December 2003. . . University of Southhampton, UK.