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MACCS2 Forum
Changes to the Computer
Code and Data Collection
CONFERENCES, COURSES,
SYMPOSIA
Fall 2005 SCALE Training Courses at ORNL
Advanced MCNP Variance
Reduction
MCNPX Workshops
230th American
Chemical Society National Meeting
Nuclear Applications of
Accelerator Technology AccApp05
International Topical
Meeting on Mathematics and Computation, Supercomputing, Reactor Physics and
Nuclear and Biological Applications
11th International Topical
Meeting on Nuclear Reactor Thermal Hydraulics
CALENDAR
An online forum for users of MACCS2 (RSICC Code
Package CCC-652) is operational at http://www.maccs2support.chaninconsulting.com/.
This is a weblog (or blog) where support is provided regarding the code's
input, models, and output. Many details of the code's internal
algorithms are not documented and are difficult to decipher, even with
examination of the source code. This forum will create a searchable
archive of questions and answers for the benefit of current and future code
users.
CCC-704/SlideRule 1.0
The Nuclear Criticality Slide Rule (SlideRule) code system,
a rapid PC-based tool for estimating pertinent information needed to guide
the actions of response teams and to help characterize some types of nuclear
criticality accidents, was developed at Oak Ridge National Laboratory, Oak
Ridge, Tennessee. It was released by RSICC in January 2002.
In July 2004, the developers and RSICC sent a notice
regarding dose terminology and the Solve capability of the electronic
version of the Nuclear Criticality Slide Rule to all recipients of the
package. The notice was also posted in the RSICC document at that time. A new
user recently contacted us about this problem. To increase the visibility of
the notice, we have added the notice in a separate file on the distribution
CD; it is also printed below.
All reported radiation absorbed
doses (rads) are tissue-dose estimates, not free-air-dose estimates.
The Solve capability for each of the five types of
incidents can provide erroneous results for the determination of specific
(i.e., Neutron, Gamma, Neutron Skyshine, Gamma Skyshine, Total Skyshine)
Estimated Prompt Doses Based on Total Fission Yield and Distance from
Incident (i.e., the lower left figure). The Total Radiation and
Total Skyshine are calculated correctly. When using the Solve feature
for the lower left figure to determine the prompt dose of a specific
radiation source (i.e., Neutron, Gamma, Neutron Skyshine, Gamma and Skyshine)
one must approach the solution in a reverse mode. That is, iteratively
solve for a known parameter (e.g., Total Fissions or Distance) by
changing a specific dose value until the desired Total Fissions and
Distance is returned by the Solver.
References: NUREG/CR 6504, Vol. 1 & 2 (ORNL/TM
13322/V1 & V2). Visual C++; PC (Pentium or later), Windows 95/NT or later
(C00704PC58601).
CCC-725/ SCALE5
The official SCALE 5 Manual, ORNL/TM-2005/39, was
published in April 2005. A CD containing the newly published SCALE 5 manual
was sent to all recipients of the initial release of SCALE 5
(C00725/MNYCP/01) by the SCALE development team and RSICC. If you obtained
SCALE5 from RSICC and have not yet received the replacement CD, please send
email to pdc@ornl.gov
and request a copy. Be sure to provide your full name and address.
The initial SCALE 5 release contained a draft
version of the manual. The new CD contains the official documentation for the
package and includes revisions and corrections. It supersedes the draft
version of the manual distributed with SCALE 5. We ask that you begin
using this official version of the manual immediately.
The manual has been updated in the SCALE 5 package now
distributed by RSICC. No other changes were made to the package at this time.
SCALE 5.1, to be released later this year, will be announced in the SCALE and
RSICC websites and newsletters. At that time we recommend that you request
the new package. Reference: ORNL/TM-2005/39 (April 2005). FORTRAN 95 and C;
DEC, IBM RS/6000, and SUN Unix workstations; Linux, and Windows 2000/XP
(C00725/MNYCP/01).
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 chronological list of the conferences. More details (if available) are
provided following the table.
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Date
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Title
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Registration
Fee*
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Description
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October
1721, 2005
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SCALE
Source Terms and Shielding Course
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$1800
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SCALE
shielding and depletion/decay sequences (including ORIGEN-ARP)
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October 2428, 2005
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KENO V.a
Criticality Safety Course
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$1800
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CSAS/KENO V.a
(including KENO3D and GeeWiz
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October
31
November 3, 2005
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TSUNAMI
Sensitivity/Uncertainty Tools
(Experienced KENO users only)
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$1500
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1-D
and 3-D sensitivity/uncertainty analysis using XSDRNPM and KENOV.a
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*A late fee of $300 will be
applied after September 17, 2005. A discount of $600
per each additional week will be applied for registration to
multiple courses. Course descriptions can be found at http://www.ornl.gov/sci/scale/training.htm.
SCALE Source Terms and Shielding Course
The SCALE Source Terms and Shielding Course
covers SAS2 and ORIGEN-ARP (depletion/source-term generation), SAS1/XSDRNPM
(1-D neutron/gamma shielding), SAS4/MORSE-SGC (3-D Monte
Carlo neutron/gamma shielding), and QADS/QAD-CGGP (3-D point
kernel gamma shielding). The course will feature the use of the SCALE
Windows GUIs: OrigenArp for Windows, ORIGEN-S plotting utility PlotOPUS,
and the ESPN shielding input processor for SAS4.
KENO V.a Criticality Safety Course
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 code that has been in use for 20
years. It is a fast, easy-to-use code that allows users to build complex
geometry models using basic geometrical bodies of cuboids, spheres,
cylinders, hemispheres, and hemicylinders. Two-dimensional color plots of
the geometry model can be generated in KENO V.a or the model may be viewed
using the KENO3D 3-D visualization
tool.
TSUNAMI Sensitivity/Uncertainty for Criticality Safety Course
Sensitivity coefficients produced by the TSUNAMI
sequences predict the relative changes in a systems calculated k-eff value
due to changes in the neutron cross-section data. TSUNAMI produces
sensitivity data on a groupwise basis for each region defined in the system
model. First-order perturbation theory is used to compute sensitivity
coefficients from both cross-section and flux data. TSUNAMI folds the
sensitivity data with cross-section covariance data to calculate the
uncertainty in the calculated k-eff value due to tabulated uncertainties in
the cross-section data. The applicability of benchmark experiments to the
criticality validation of a given application can be assessed using
S/U-based integral indices that can quantify system similarity. Attendees
must have attended a KENO course or be experienced KENO users.
An
Advanced MCNP Variance Reduction class for the MCNP (Monte Carlo
N-Particle) transport code will be held in Los Alamos, NM,
August 2325, 2005. This class will be taught by the team that develops and
maintains MCNP.
The
class will focus specifically on using variance reduction methods in MCNP.
Basic experience with MCNP is required. The class will include interactive
computer sessions with PC's running Microsoft Windows.
The course will be a mixture of theory and
practice. Specific topics include: mean and variance, score distribution
vs. mean distribution, central limit theorem, intuitive notions of variance
reduction, MCNP variance reduction techniques, how the weight window
generator works, deficiencies of biasing by importance function, how not to
use dxtran, when to stop attempting more variance reduction, reading an
event log, comments on Monte Carlo and equations, weight in MCNP and
Monte Carlo, and variance reduction for the pulse height tally (f8).
Detailed information and registration is
available at http://laws.lanl.gov/x5/MCNP/aug05var.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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Aug. 812
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Intermediate
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Seoul, Korea
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Sept. 59
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Advanced
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Bologna, Italy
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Sept. 1923
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Intermediate
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Washington, D.C.
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Nov.
711
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Introductory
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Santa Fe, NM
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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.
Applied Modeling and Computations in
Nuclear Science will be held in Washington,
DC, August 28September
1, 2005. The meeting is sponsored by the Division of Nuclear Chemistry and Technology
(NUCL) of the American Chemical Society (ACS), and the American Nuclear
Society (ANS). The purpose of this symposium is to bring theoretical and
computational work in applied nuclear science under one umbrella, so that
the nuclear scientists interested in modeling have a broader forum for
their research, as well as to enable learning related techniques.
Cross-disciplinary computations are also of interest. Tentative topics
include:
1. Statistical
aspects of radioactivity, such as uncertainties, detection limits, novel
statistics.
2. Radiation
transport methods (Monte Carlo and deterministic), and nuclear data
evaluations.
3. Calculating
of the response and theoretical designing of radiation detectors.
4. Spectral
deconvolution and fitting: alpha, beta, gamma spectroscopy.
5. Calculations
of chemical structure and reactions involving radionuclides.
6. Transport
models of radioactive contaminants in the environment.
7. Health
physics calculations: dosimetry and risk assessment.
8. Medical
radiation physics calculations: radiotherapy and imaging.
9. Nuclear
sensing: modeling of well logging and gauges.
10. Computers in nuclear science
laboratory, QA/QC, LIMS, etc.
11. Novel and sophisticated methods
of nuclear data analysis.
12. Nuclear modeling of interest to
counter-terrorism.
13. Novel computational algorithms
of interest to applied nuclear science.
Registration and housing reservations will
be available on-line in June and the final program appears in C&EN and
on the ACS web page in June/July 2005. Full papers are due at the
conference August/September 2005 in MS Word format only. Instructions will
be distributed to the accepted speakers.
The ACS web page is www.chemistry.org.
For further information please contact Thomas Semkow, Wadsworth Center, New
York State Department of Health and SUNY, P.O. Box 509, Albany, NY
12201-0509, phone: +518-474-6071, fax: +518-474-8590, email: tms15@health.state.ny.us.
The complete announcement as submitted by Thomas M. Semkow can be found at http://www.cofc.edu/~nuclear/2005WashingtonComputationSymposium.pdf.
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 28September 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.
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 1215,
2005.
The
meeting offers an environment for interdisciplinary exchange among
researchers 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/.
NURETH is the foremost international
technical meeting on nuclear technology thermal hydraulics. The French
Section of the American Nuclear Society is very proud to organize and
announce that the Eleventh Nureth Topical Meeting will be held in Avignon, France
on October 2-6, 2005, in the historic Palace of the Popes in Avignon, France, October 26, 2005.
The main
topics covered by the Nureth 11 meeting will be devoted to the
thermal-hydraulics of existing and future nuclear power plants as foreseen
by the Generation IV worldwide initiative. Normal operation and accidental
situations are relevant topics of the conference. Topics encompass
modeling, experiments, instrumentation and numerical simulations related to
flow and heat transfer in nuclear reactors with a special emphasis on the
advances of multiphase CFD methods.
For
more information please go to http://nureth11.com/.
August 2005
MCNPX Workshop, Aug. 812, 2005, Seoul, Korea.
Contact: Bill Hamilton (phone 806-928-6021, email bill@mcnpxworkshops.com,
url http://mcnpxworkshops.com
for details).
12th International Conference on Emerging Nuclear
Energy Systems (ICENES 2005), Aug. 2126, 2005, Brussels, Belgium.
For more information: http://www.sckcen.be/
sckcen_en/activities/conf/conferences/icenes2005/date_place.shtml.
MCNP Advanced Variance Reduction class, Aug. 2325,
2005, at Los Alamos National Laboratory. Contact: Cheryl Royer (croyer@lanl.gov,
phone: 505-665-2154, http://laws.lanl.gov/x5/MCNP/aug05var.html.)
Seventh Topical Conference on Nuclear Applications of
Accelerator Technology AccApp05, Aug. 28Sept. 1, 2005, Venice, Italy.
For more information: http://www.nea.fr/listsmh/satif/pdf00004.pdf.
Applied Modeling and Computations in Nuclear Science,
Aug. 28Sept. 1, 2005, Washington,
DC. Contact Thomas Semkow
(phone +518-474-6071, fax +518-474-8590, email tms15@health.state.ny.us).
September 2005
XIX Nuclear Physics Divisional Conference (NPDC19) of
the European Physical Society, Sept. 59, 2005, Pavia, Italy.
Contact: Saverio Altieri (email saverio.altieri@pv.infn.it, url http://www.pv.infn.it/~npdc19).
MCNPX Advanced Workshop, Sept. 59, 2005, Bologna, Italy. Contact: Bill Hamilton
(phone 806-928-6021, email bill@mcnpxworkshops.com, url http://mcnpxworkshops.com
for details).
International Topical Meeting on Mathematics and
Computation, Supercomputing, Reactor Physics and Nuclear Biological
Applications (M&C 2005), Sept. 1215, 2005, Avignon, France.
Contact: Dr. Richard Sanchez (email avignon2005@drnsac.cea.fr;
url http://mcavignon2005.cea.fr).
MCNPX Intermediate Workshop, Sept. 1923, 2005, Boston, MA, or Washington, D.C.
Contact: Bill Hamilton (phone 806-928-6021, email bill@mcnpxworkshops.com,
url http://mcnpxworkshops.com).
2005 NCSD Topical Meeting, Sept. 1922, 2005, Knoxville, TN.
For more information: http://meetingsandconferences.com/ncsd2005/.
October 2005
11th International Topical Meeting on Nuclear Reactor
Thermal Hydraulics, Oct. 26, 2005, Avignon,
France.
For more information: http://nureth11.com, nureth11@cea.fr.
10th Workshop on Monte Carlo Simulation of
Radiotherapy Treatment Sources using the BEAM Code System, Oct. 36, 2005,
Ottawa, Canada. Contact: Dave Rogers, Physics Department, Carleton
University, 1125 Colonel By Drive, Ottawa, Ontario, Canada, K1S 5B6 (tel
613-520-2600x4374, fax 613-520-4061, e-mail drogers@physics.carleton.ca,
url www.physics.carleton.ca/~drogers/BEAM/course/brochure.html.)
SCALE Source Terms and Shielding Course, Oct. 1721,
2005, Oak Ridge National Laboratory, Oak
Ridge, TN. Contact: http://www.ornl.gov/sci/scale/training.htm.
KENO V.a Criticality Safety Course, Oct. 2428, 2005,
Oak Ridge National Laboratory, Oak
Ridge, TN. Contact: http://www.ornl.gov/sci/scale/training.htm.
TSUNAMI Sensitivity/Uncertainty Tools, Oct. 31Nov.
3, 2005, Oak Ridge National Laboratory, Oak Ridge, TN. Contact: http://www.ornl.gov/sci/scale/training.htm.
November 2005
MCNPX Introductory Workshop, Nov. 711, 2005, Santa Fe, NM.
Contact: Bill Hamilton (phone 806-928-6021, email bill@mcnpxworkshops.com,
url http://mcnpxworkshops.com
for details).
ANS Winter Meeting and Nuclear Technology Expo, Talk
About Nuclear Differently: A Good Story Untold, November 1317,
2005, Washington,
D.C. Contact: http://www.ans.org/meetings/.
March 2006
HEART Conference, March 610, 2006, Sunnyvale, CA. Contact: Technical Program
Chair, Dennis Breuner (phone 858-720-7072, email dbreuner@titan.com).
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