Post Office Box 2008
Oak Ridge, Tennessee 37831-6171
Managed by
UT-Battelle, LLC
for the U.S. Department of Energy
under contract DE-AC05-00OR22725
Phone No. 865-574-6176 FAX 865-241-4046
Internet PDC@ORNL.GOV
http://rsicc.ornl.gov
| Radiation Safety Information Computational Center | |
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Oak Ridge National Laboratory Post Office Box 2008 Oak Ridge, Tennessee 37831-6171 Managed by Phone No. 865-574-6176 FAX 865-241-4046 |
| No. 480 | February 2005 |
| "Democracy is never a thing done. Democracy is always something that a nation must be doing. Archibald MacLeish | |
The RSICC website moved to a new server the last weekend in January. The dust is still settling around our new URL. Some unexpected problems arose. We are still fine tuning the system, so there may be some minor changes over the next few days. Your links to the RSICC home page should work, but bookmarks to subdirectories and forms maynot. We recommend that you use http://rsicc.ornl.gov.
Note that the site will be down February 12 for at least 15 hours. We apologize for any inconvenience these changes may have caused.
Obituary—Herbert Goldstein,
Nuclear Scientist—RSICC Friend
Dr. Herbert Goldstein (June 26, 1922–January 12, 2005), professor emeritus of nuclear cience and engineering at Columbia University, book author, and research scientist, died in New York City on January 12, 2005. He was buried in Israel.
Professor Goldstein was long recognized for his
scholarship in classical mechanics and reactor shielding. His
Classical Mechanics graduate textbook was translated into nine
languages, and has been widely used as the standard text in the field
since it first appeared in 1950. While a consultant for Brookhaven and
Oak Ridge National Laboratories, he became interested in radiation transport
and shielding. He published in 1958 (reprinted 1971) Fundamental Aspects
of Reactor Shielding, a basic discussion of radiation sources, interaction
with matter and attenuation concepts.
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He became interested in the information analysis center concept
as a means to advance
the state-of-the-art of shielding at a faster pace and supported the
Radiation Shielding
Information Center (RSIC) from its beginning in 1962. He chaired an Ad
Hoc Advisory
Committee (Goldstein, Viktor Hampel of Livermore and Gerald Lahti of
Sargent & Lundy),
February 7-8, 1977, to evaluate RSIC in terms of operations and service
to the nuclear industry.
The findings of the study were positive and were useful in support of
RSIC as a national asset
to its sponsors and user community. The information center continues
with extended coverage
as RSICC.
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An early member of the American Nuclear Society (ANS), Goldstein was the first vice chairman of the original Shielding Division (SD) (1961-1962) and second chairman (1962-1963). In 1977, he was honored by the division as the recipient of the ANS/SD Distinguished Service Award. He was honored as an ANS Fellow (1962), Rockwell Lifetime Achievement, ANS Radiation Protection and Shielding Division (1989), and the ANS Arthur Holly Compton Award (1989).
Dr. Goldstein was a professor of nuclear science and engineering in the School of Engineering and Applied Science at Columbia since 1961. He received the Great Teacher Award, given by the Society of Columbia Graduates, in 1976. In 1984 he was the first to hold the Thomas Alva Edison professorship at the University. Appointment to a named chair is one of the highest honors bestowed on a university scholar.
He was a Fellow of the American Physical Society, the New York Academy of Sciences, and the American Association for the Advancement of Science. He was a member of the American Association of Physics Teachers, and he was a founding member and served as president of the Association of Orthodox Jewish Scientists. He received his B.S. from City College of New York in 1940 and his Ph.D. from the Massachusetts of Technology in 1943.
He is survived by his wife Channa, his children, Penina, Aaron Meir, and Shoshanna, and ten grandchildren.
-Betty F. Maskewitz
Change to the Computer Code and Data Collection
CCC-684/NRCDose 2.3.5
OP SYS: Windows
Language: FORTRAN + Visual Basic
Computers: PC
Chesapeake Nuclear Services, Inc., and J. Stewart Bland Associates, Inc., Annapolis, Maryland, contributed a newly frozen version of this suite of NRC computer codes used for evaluating routine radioactive effluents from nuclear power plants. NRCDose includes LADTAP II, GASPAR II, and XOQDOQ with a WINDOWS interface to facilitate ease of use. It is intended for modeling routine, normal effluents under annual average environmental conditions and should not be used for accident dose assessment.
NRCDose runs on Pentium computers under Windows operating systems. The
distributed executables were created with the Microsoft Fortran
PowerStation Version 4.0. and
Microsoft Visual Basic 6.0. The codes were tested under Windows XP and
Windows2000.
Source files are not included, so this code system can be run only on
PCs under Windows. The
package is transmitted on CD in Windows format. References: User’s
Guide, (November 14,
2000, revised 2003); 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 and Visual Basic; Pentium (C000684PC58604).
CONFERENCES, COURSES, SYMPOSIA
RSICC attempts to keep its users and contributors advised of conferences, courses, and symposia in the field of radiation protection, transport, and shielding through this section of the newsletter. Should you be involved in the planning/organization of such events, feel free to send your announcements and calls for papers via email to riceaf@ornl.gov with “conferences” in the subject line by the 20th of each month. Please include the announcement in its native format as an attachment to the message. If the meeting is on a website, please include the url.
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. Below is a condensed list of the conferences listed chronologically. More details (if available) are listed alphabetically following the table.
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A four-day introductory class for the MCNP (Monte Carlo N-Particle) transport code will be held at LANL February 22-25, 2005. This class will be taught by the team who develops and maintains MCNP.
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.
Costs: Cost for the class is $1,800. There is a $300 discount if payment is received by February 14th, 2004. Radiation Safety Information Computational Center (RSICC) provides the code and data package and documentation after the class is over at their lowest tier price.
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 class, go to http://www-xdiv.lanl.gov/x5/MCNP/classinformation.html.
Lead Teachers: Drs. John Hendricks, Gregg McKinney, Laurie Waters
Organizer: HQC Professional Services Contact: bill@mcnpxworkshops.com
More
Information: http://mcnpxworkshops.com
MCNPX homepage:
http://mcnpx.lanl.gov
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Feb. 28-Mar. 4 |
Intermediate |
Mol, Belgium |
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June 13-17 |
Introductory |
Santa Fe, CA |
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Aug. 1-5 |
Introductory |
Seoul, Korea |
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Sept. 19-23 |
Intermediate |
Boston or D.C. |
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Nov. 7-11 |
Introductory |
Santa Fe, CA |
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 and is 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.
The 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.
Monte Carlo 2005 Topical
Meeting
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 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
Using MCNP5 for Medical Physics Applications
Sponsor: Computational Medical Physics
Working Group
Cost: Free
Sunday, April 17, 2005, 1-5PM at the Monte
Carlo 2005 Conference at the Chattanooga
Convention Center, Chattanooga, Tennessee. (http://montecarlo2005.org
)
“Using MCNP5 for Medical Physics Applications,” by Tim Goorley of the MCNP Development Team, X-5, Los Alamos National Laboratory, and Dick Olsher of the HSR - 4, Los Alamos National Laboratory.
Monte Carlo techniques are increasingly popular in many medical physics
applications. This half-day tutorial focuses on how to use new and old
MCNP5 features for neutron, photon
and electron transport problems. The tutorial will include handouts and
some demonstrations
by the instructor, but not hands-on computer activities for the student
The following is a draft of
the topics which will be covered:
1) Overview of new MCNP5 features
a) Mesh tallies,
b) Photon Doppler Broadening,
c) > 2.1 billion histories,
d)Lattice tally enhancements
2)Geometries and Modelling
b) MIRD Phantoms,
b) CT_based geometries
3) Sources
4) Tallies
a) Calculating dose w/ different tallies,
b) Flux to Kerma factors (DE DF cards),
c) Calculating reaction rates
5) Misc
a) S(alpha, beta) neutron scattering treatment,
b) Simple variance reduction,
c) Benchmarking Studies - QUADOS,
d) using PTRAC file for coincident counting.
2005
International Congress on Advances in
Nuclear Power Plants (2005 ICAPP)
The 2005 International Congress on Advances
in Nuclear Power Plants will be held from
May 15-19, 2005, in Seoul, Korea.
There is no doubt that continuing support and
interest will be a crucial element for the success of the first ICAPP
held in Asia.
The ICAPP has grown in stature since the first congress was held in 2002 to share
ideas and visions for advances in nuclear power plants among operators,
researchers and scholars. The 2005 ICAPP will attract the attention of the world's
nuclear experts with many outstanding presentations of new developments and approaches in various
studies and industrial projects. Please take the opportunity to share the results
of your latest studies at the 2005 ICAPP. To ensure a successful congress, the 2005 ICAPP will
consist of invited plenary sessions and topical technical sessions, as follows:
Visit the website
Electron-Photon Transport
Modelling with PENELOPE-2005 -
Physics, Code Structure and Operation
PENELOPE is being updated to include several new features and an updated database. An advanced training course/workshop entitled “Electron-Photon Transport Modelling with PENELOPE-2005 - Physics, Code Structure and Operation” is scheduled for 4–7 July 2005, at the Facultat de Fisica (ECM), Universitat de Barcelona, Diagonal 647, 08028 BARCELONA, Spain.
This course is addressed to researchers in radiation physics and its applications. The main objective is to provide the participants with a detailed description of PENELOPE-2005 with an ample perspective on Monte Carlo methods for simulation of electron/photon transport. The reliability of the interaction models and the accuracy of the numerical methods and approximations implemented in the code will be discussed. Examples of simulation results and benchmark comparisons with experiment will be presented. The course will include practical sessions on the use of the generic main programs, PENCYL (cylindrical geometries) and PENMAIN (quadric geometries), and on the design of the main program for specific applications.
Accommodation at the facilities of the University will be available and the weather is known to be very pleasant then. The deadline for registration is 30 April 2005. Links to the syllabus and registration form may be found at http://www.nea.fr/html/dbprog/Newsletter/Dec2004.htm#training .
International
Topical Meeting on Mathematics and
Computation, Supercomputing, Reactor Physics and
Nuclear and Biological Applications
The International Topical Meeting on Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications will be held at the ‘Palais des Papes,’ Avignon, France, September 12-15, 2005.
The meeting offers an environment for interdisciplinary exchange among research in the nuclear field and comprises 19 General Technical sessions and 13 Invited Technical sessions. Details on the sessions and on the organization of the meeting are given at the web site: http://mcavignon2005.cea.fr/.
Papers are solicited in all areas of computational and mathematical methods and related disciplines including reactor physics, material sciences, shielding, fluid-dynamics, medical and biological applications, environmental sciences, fundamental mathematics and benchmarking.
We are now less than one year from the meeting dates and our web has been opened for the submission of extended summaries (1000 words < 1500 words). The deadline for summary submission is January 15, 2005.
Instructions
on summary submission are given in the web pages under the
‘Authors’ button.
Practical
MCNP for the Health Physicist,
Medical Physicist, and Rad Engineer
DATES: June 6 -10, 2005 (4.5 days)
FEE: $1,450 per person
PLACE: The MESA Complex, Room 130, University of New Mexico-Los Alamos Campus
Monte Carlo 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 personal computers. 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:
Please note that this course is separate from and independent of the courses
being offered by the MCNP and MCNPX Teams at LANL.
Nuclear Applications of Accelerator Technology “AccApp05”
The forthcoming International Topical Meeting on Nuclear Applications of
Accelerator Technology (AccApp'05) is the seventh in a series of international
meetings of the Accelerator Applications Division of the ANS. It is scheduled
for August 28-September 1, 2005, on the
Island of San Servolo, Venice, Italy. The purpose of AccApp'05 is to
provide an international forum for presenting and discussing the use of particle accelerator
technology for a variety of applications. It is intended to focus on a wide area of applications
including, spallation neutron sources, isotope production, medical therapy, nuclear waste
transmutation, energy production, high power accelerators under construction and future projects,
material issues in a particle environment, nuclear data and experiments, codes and models for
particle transport, system engineering, thermo hydraulics, contraband detection and radiation
protection. For more information see: http://www.nea.fr/listsmh/satif/pdf00004.pdf
Eleventh
International Topical Meeting on Nuclear Reactor
Thermal Hydraulics
NURETH is the foremost international
technical meeting on nuclear technology thermal
hydraulics. The NURETH-11 meeting will be held in the historic Palace
of the Popes in
Avignon, France, October 2-6, 2005.
For more information please go to http://nureth11.com/.
Reactor
Dosimetry - 12th International Symposium
Approximately every three years the ASTM International Committee E10 on Nuclear
Technology and Applications and the European Working Group on Reactor
Dosimetry organize a symposium on reactor dosimetry. The 12th International Symposium on
Reactor Dosimetry will be held in Gatlinburg, Tennessee, May
8-13, 2005. This symposium will be of interest to
anyone involved in reactor dosimetry, including researchers,
manufacturers and representatives
from industry, utilities and regulatory agencies. The symposium theme
is dosimetry for the assessment of irradiated reactor materials and reactor experiments,
featuring radiation metrology techniques, data bases and standardization. Additional
information on paper submittal and specific focus topics can be obtained by visiting the
Symposium's web site http://www.reactordosimetry.com
.
In addition to the 100 to 120 oral and poster papers on
the topics given on the web site, the symposium will feature six
informal round-table workshops
and two introductory level tutorials. The workshops will focus on
discussions of problems,
conflicts, recommendations, news and ideas. The workshop titles for the
12th Symposium will
be: Accelerators and Fusion, Adjustments Methods and Uncertainties,
Cross Section Files and
Uncertainties, LWR Surveillance Dosimetry, Radiation Damage
Correlations, and Test and
Research Facilities. The two introductory level tutorials will be held
in parallel and will address
the topics of “Radiation Effects in Reactor Materials” and “Neutron
Scattering Applications in
Material Science.
This symposium is a must-attend meeting for those
serious about the field
of radiation dosimetry and will offer the opportunity for sharing ideas
and discussions with
colleagues in the field of radiation dosimetry. This meeting will also
be ideal for those new to
the field who want to be up to date on dosimetry related issues.
February 2005
Waste Management '05, Feb. 27-Mar. 3, 2005, Tucson, AZ. Contact: Michelle Rehmann (Tech. Program Cord., tel 520-696-0399; email michelle_rehmann@ wmarizona.org url www.wmsym.org ).
MCNPX Intermediate Workshop, Feb. 28-Mar. 4, 2005, Mol, Belgium. Contact: Bill Hamilton (tel 505-455-0312, email bill@mcnpxworkshops.com , url http://mcnpxworkshops.com for details).
March 2005
Forty-First Annual Meeting of the National Council on Radiation Protection and Measurements, Mar. 30-31, 2005, Arlington, VA. Additional information: http://www.ncrp.com.
April 2005
AIChE Spring National Meeting, Apr. 10-14, 2005, Atlanta, GA. Contact: James J. Laidler (630-252-4479, fax 630-972-4479, email laidler@cmt.anl.gov url http://www.aiche.org/conferences/ ).
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://MonteCarlo2005.org ).
May 2005
12th International Symposium on Reactor Dosimetry, May 8-13, 2005, Gatlinburg, TN. Contact: Dr. James M. Adams (tel 301-975-6205, fax 301-926-1604, url http://reactordosimetry.com ).
Radiation Transport Calculations Using the EGS Monte Carlo System, May 9-13, 2005, Ottawa, Canada. Contact: Nikki Dignard (tel 613-520-4388, fax 613-520-4389, email NikkiDignard@pigeon.carleton.ca, url http://www.physics.carleton.ca/~drogers/EGScourse05/).
1st International Nuclear Chemistry Society (INCS), May 22-29, 2005, Kusadasi, Turkey. For more information: http://incs.ege.edu.tr/ 1st-INCC.html.
June 2005
ANS Annual Summer Meeting, June 5-9, 2005, San Diego, CA. For more information: url http://www.ans.org/meetings/ .
MCNPX Introductory Workshop, June 13-17, 2005, Santa Fe, CA. Contact: Bill Hamilton (tel 505-455-0312, email bill@mcnpxworkshops.com , url http://mcnpxworkshops.com for details).
July 2005
PENELOPE-2005 Training Course, July 4-7, 2005, Barcelona, Spain. http://www.nea.fr/html/dbprog/Newsletter/Dec2004.htm#training .
August 2005
MCNPX Workshop, Aug. 1-5, 2005, Seoul, Korea. Contact: Bill Hamilton (tel 505-455-0312, email bill@mcnpxworkshops.com , url http://mcnpxworkshops.com for details).
12th International Conference on Emerging Nuclear Energy Systems (ICENES 2005), Aug. 21-26, 2005, Brussels, Belgium. For more infomation: http://www.sckcen.be/ sckcen%5Fen/activities/conf/conferences/icenes2005/ .
Seventh Topical Conference on Nuclear Applications of Accelerator Technology “AccApp05”, Aug. 28-Sept. 1, 2005, Venice, Italy. For more information: http://www.nea.fr/ listsmh/satif/pdf00004.pdf.
September 2005
XIX Nuclear Physics Divisional Conference (NPDC19) of the European Physical Society, Sept. 5-9, 2005, Pavia, Italy. Contact: Saverio Altieri (email saverio.altieri@pv.infn.it , url http://www.pv.infn.it/~npdc19 ).
International Topical Meeting on Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear Biological Applications (M&C 2005), Sept. 12-15, 2005, Avignon, France. Contact: Dr. Richard Sanchez (email avignon2005@drnsac.cea.fr ; url http://mcavignon2005.cea.fr ).
MCNPX Intermediate Workshop, Sept. 19-23, 2005, Boston, MA, or Washington, D.C. Contact: Bill Hamilton (tel 505-455-0312, email bill@mcnpxworkshops.com , url http://mcnpxworkshops.com for details).
2005 NCSD Topical Meeting, Sept. 19-22, 2005, Knoxville, TN. For more information: http://meetingsandconferences.com/ncsd2005/ .
October 2005
Eleventh International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Oct. 2-6, 2005, Avignon, France. For more information: http://nureth11.com, nureth11@cea.fr.
November 2005
MCNPX Introductory Workshop, Nov. 7-11, 2005, Santa Fe, CA. Contact: Bill Hamilton (tel 505-455-0312, email bill@mcnpxworkshops.com , url http://mcnpxworkshops.com for details).