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Changes
to the Computer Code and Data Collection. 1
PSR-530/BOT3P-5.0. 1
News
to Note from ANS. 2
Tonozuka
Announced Head of Japan Atomic Energy Agency. 2
U.S.
DOE to Establish Beijing Office. 2
University
of Manchester Launches New Nuclear Institute. 3
Obituaries. 3
RPI
Nuclear Engineering Faculty Positions. 3
CONFERENCES,
COURSES, SYMPOSIA.. 4
Fall
2005 SCALE Training Courses at ORNL. 4
SCALE
Source Terms and Shielding Course. 4
KENO
V.a Criticality Safety Course. 4
TSUNAMI
Sensitivity/Uncertainty for Criticality Safety Course. 5
MCNPX
Workshops. 5
MCNP
Special Topics Criticality Class. 6
TRAINING
COURSE ON NEUTRON SPECTRA UNFOLDING.. 6
Radiation
Process Simulation and Modeling User Group
Annual Meeting. 7
ANS
RP&S Division Biennial Topical Meeting. 7
PHYSOR
2006. 7
CALENDAR.. 8
ENEA
Nuclear Data
Center, Bologna, Italy,
contributed this code system for 2D and 3D mesh generation and graphical
display of geometry and results for deterministic transport codes.
Bologna Transport Analysis Pre-Post-Processors (BOT3P) is a set of
standard Fortran 77 language programs developed at the ENEA -Bologna Nuclear Data
Center. BOT3P Version 1
was conceived to give the users of the DORT
and TORT deterministic transport codes, included in the CCC-650/DOORS 3.2 or
DOORS3.2a software package, some useful diagnostic tools to prepare and check
their input data files. Later versions were extended for compatibility with
TWODANT and THREEDANT, the SUSD3D cross section sensitivity and uncertainty
code, and MCNP.
BOT3P Version 5.0 (BOT3P-5.0) contains
important additions such as, new 2D and 3D graphics options, more detailed
standard output information and the possibility to directly manage and plot
2D R-Z geometries. The most significant new feature of BOT3P-5.0 regards the
mesh generation programs. Users can optionally calculate the area/volume
error of material zones with respect to the theoretical values and the
automatic correction of material densities and uniformly distributed neutron
sources to globally preserve masses and neutron sources, respectively.
Moreover, a binary file is optionally written with the density distribution
of the different materials contained in the single mesh, allowing a local
density correction (per mesh) in alternative to a global density correction
on the whole domain of the material zone. This ‘fine’ material distribution
can optionally be visualized by the 2D plot BOT3P-5.0 modules DDM, DTM2.
Also included in the
package is ADEFTA, which is a script file that calculates the atomic densities related to any compositional model for
transport analysis. The output produced by ADEFTA can be useful for
applications with many transport codes and is particularly applicable to
users of GIP, DORT and TORT (DOORS)
and the Monte-Carlo MCNP code. ADEFTA runs on UNIX/Linux platforms using
Bourne Shell commands and the “awk” utility.
The package is transmitted as a GNU
compressed UNIX tar file on a CD. The tar file contains the source files for
all programs in the auxiliary codes list, test cases, implementation
instructions, procedures, description of sample problem cases, and
documentation. Reference: FIS P9H6-008 (April 2005). DEC Alpha, Linux PC, IBM
RS/6000 (P00530/MNYCP/00).
Tonozuka
Announced Head of Japan
Atomic Energy Agency
Yuichi Tonozuka
will head the Japan Atomic Energy Agency (JAEA), a new research organization
created from the merger of the Japan Nuclear Cycle Development Institute
(JNC) and the Japan Atomic Energy Research Institute (JAERI). The JAEA will
be Japan’s
only comprehensive nuclear R&D organization; its primary focus will
include the fast breeder reactor cycle, nuclear fusion, and disposal of
high-level radioactive waste. Tonozuka said he
intends to “build something new” by fusing the traditions of the two—JAERI’s basic research and JNC’s
more project-oriented research.
Nuclear
News, Sept. 2005, p 40
U.S.
DOE to Establish Beijing
Office
In conjunction
with the first meeting of the U.S.-China Energy Policy Dialogue, held in Washington, D.C., the
U.S. Department of Energy announced on June 30 the establishment of an office
in Bejing to support the Department’s cooperative
efforts with China
on energy and nuclear security issues. The office will be located in the U.S.
Embassy in Beijing.
Energy Secretary Samuel Bodman said, “Through the
U.S.-China Energy Policy Dialogue, and with on-site assistance from the new
DOE office, we can enhance our cooperation to promote energy efficiency,
diversify our energy supplies, expand the use of clean energy technologies,
as well as continue our mutual efforts to increase nuclear security in both
our nations.”
Nuclear
News, Sept. 2005, p 40
University
of Manchester
Launches New Nuclear Institute
A ceremony at the University of Manchester
on July 18 launched the new Dalton Nuclear Institute. The Institute’s
research will include electricity generation, fuel cycles, waste treatment
and disposal, decommissioning, policy, and regulation. It will also tie its
research into advancing areas such as nuclear medicine and fusion. The
Institute is named for John Dalton, who joined with Manchester
businessmen and industrialists in 1824 to establish the Mechanics’ Institute,
which became the University
of Manchester, to
ensure that workers could learn the basic principles of science. In 1803, Dalton unveiled his
atomic theory which was the basis for all subsequent chemical investigations.
Richard Clegg, formerly with British Nuclear Fuels plc, is the first director
of the Institute. He said, “By 2015, if people want to do nuclear research,
they will have the choice to go to two or three leading universities in the
world, and Manchester
will be one of them.”
Nuclear
News, Sept. 2005, p 41
Ray H. Crist died July 23 in Carlisle, Pennsylvania;
he was 105. He is believed to be the oldest published
research scientist in history. A chemist, he joined the faculty of Columbia University in 1925. He joined the
Manhattan Project in 1941 to help produce the atomic bomb. In 1946 he became
a researcher for Union Carbide. At 63 he retired from the corporate sector
and returned to teaching; he taught the history of science at Dickenson College
(1963–1970) and environmental chemistry at Messiah College
(1974–2004). During the last two decades at Messiah he performed innovative
experiments involving the absorption of toxic metals by plant material.
Paul V. Harper, M.D., 89, professor
emeritus in the departments of surgery and radiology at the University of Chicago,
died July 15 in Evanston,
Illinois. A pioneer in the
1950s in the diagnostic and therapeutic uses of radiation, he was a key
member of the team investigating the medical applications of dozens of
radioactive isotopes, including technetium-99m, iodine-125, and thallium, all
of which are widely used today. He was appointed to the International
Commission on Radiation Units and Measurements in 1975. Though he retired
from the University
of Chicago in 1986, he
continued to do research until last year.
Nuclear
News, Sept. 2005, p 66
The Nuclear Engineering and Engineering
Physics Program at Rensselaer Polytechnic Institute has
announced several faculty positions made available by the new dean of the School of Engineering. These tenure-track
positions are at assistant/associate/full professor levels, depending on the
qualification, and cover technical areas which include reactor physics,
applied radiation technologies, and biomedical use of radiation (i.e.,
health/medical physics with strong background in radiation transport
simulations). Please send an application with the names and the contact
information of three references to Search Committee Chair, Professor Robert Block:
Dr. Robert C. Block
Director
of Gaerttner LINAC Laboratory
Dept. of
Mechanical, Aerospace and Nuclear Engineering
Rensselaer
Polytechnic Institute
Troy, New York
12180-3590
Tel.
No.: (518) 276 6404
Fax. No.: (518) 276 4007
E-Mail
: blockr@rpi.edu
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.
Fall
2005 SCALE Training Courses at ORNL
|
Date
|
Title
|
Registration
Fee*
|
Description
|
|
October 24–28, 2005
|
KENO V.a Criticality
Safety Course
|
$1800
|
CSAS/KENO V.a (including
KENO3D and GeeWiz)
|
|
October
31–
November 3, 2005
|
TSUNAMI
Sensitivity/Uncertainty Tools
(Experienced KENO users only)
|
$1500
|
1-D
and 3-D sensitivity/uncertainty analysis using XSDRNPM and KENOV.a
|
*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 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
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 one 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 TSUNAMI
sequences predict the relative changes in a system’s 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 sensitivity data with cross-section covariance
data to calculate the uncertainty in the calculated k-eff
value due to tabulated uncertainties in 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.
MCNPX
Workshops
Lead
Teachers: Drs. John Hendricks, Gregg McKinney, Laurie Waters
Organizer:
HQC Professional Services
Contact: bill@mcnpxworkshops.com
Information: http://mcnpxworkshops.com/
and MCNPX homepage: http://mcnpx.lanl.gov/
|
2005 Schedule
|
|
Oct. 31–Nov. 4
|
Intermediate
|
Santa Fe, NM
|
|
2006 Schedule
|
|
January
9–13
|
Introductory
|
Las Vegas, NV
|
|
March
27–31
|
Intermediate
|
Capetown, South Africa
|
|
June 12–16
|
Introductory
|
Santa Fe, NM
|
The Santa Fe
workshop this fall is presently the ONLY Intermediate workshop on the U.S. schedule
for the next 9 months. If you have some experience with MCNPX and
related codes, you will benefit from this workshop. We will introduce
you to the latest features of MCNPX along with nuances of the features with
which you are already somewhat familiar.
MCNPX is packed with new and exciting
plotting features, including numerous mesh tally options which can be
superimposed on your geometry plot and plotted within the MCNPX run,
eliminating the need for post-processing and costly additional plotting
package(s). You can plot particle flux, tracks, dosage, and energy
deposition as well as source points and many others.
Other capabilities which will be featured in
the workshop include:
*
Pulse-height tallies with variance reduction
*
Radiography tallies and 2D contour plots
*
MPI and PVM multiprocessing
*
Criticality calculations 100 x faster
*
Geometry plots have 64-colors, can shade by different cell quantities, and
can label i,j,k indices
*
The ability to use physics models when cross section tables are missing
*
Physics models include Bertini, Dresner,
ISABEL, CEM2k, and INCL/ABLA
*
Photonuclear and proton plots
*
Light-ion recoil
*
3-He coincidence tallies
*
Default (built in) dose functions
*
Multi-particle sources
*
Positron sources
*
Spontaneous fission sources
*
Fission multiplicity
*
Coincidence capture tallies
* Anticoincidence pulse-height tallies
There are still places available in this
workshop.
The workshops
include hands-on instruction, generally on PC Windows
machines. Subject to participant
export approval from 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/.
A four-day special topics criticality class
for the MCNP (Monte Carlo N-Particle) transport code will be held at LANL
November 1–4, 2005. It will be taught by the team who develops and
maintains MCNP.
The class will focus on using MCNP5 to
perform criticality calculations for reactor physics and criticality safety
applications. It is an intermediate level class, intended for those with at
least some familiarity with MCNP.
Topics to be covered include:
·
Criticality calculations using Monte Carlo
methods
·
Geometry, including lattices & repeated structures
·
Tallies & mesh tallies
·
Cross-section data
·
Statistical analysis
·
Assessing convergence of K-eff & the
source distribution
·
Interactive running & plotting with MCNP5
Classes will include lectures and hands-on
computer use for a variety of criticality calculations. Time will be
available to discuss individual questions & problems with the MCNP5
development staff and to pursue additional advanced topics.
Cost for the class is $1,800, with a $300
discount applied if payment is received by Oct. 24, 2005. The class fee
includes a notebook with all class viewgraphs and handouts. Information will
be sent by follow-up letter or email when we receive your registration
information.
To register for the class, go to http://laws.lanl.gov/x5/MCNP/classinformation.html.
This
two-day training course on neutron spectra unfolding will be held April 7–8,
2006, in Cape Town, South Africa. The training course
is organized by the Neutron Radiation department of the Physikalisch-Technische
Bundesanstalt (PTB), Braunschweig, Germany. Additional support is
provided by EURADOS. The course is intended for those who do spectrometry in
neutron or mixed neutron/photon fields and need to analyze their data using
unfolding procedures; emphasis is on practical aspects of unfolding.
A series
of lectures in the morning sessions will provide an introduction to unfolding
as well as allow for discussions on the theory of unfolding. In the afternoon
sessions participants will work on specific examples at PC-workplaces using
the UMG software package provided by PTB (UMG: Unfolding with GRAVEL and
MAXED, currently distributed by NEA as code package NEA-1665 and by RSICC as
code package PSR-529). We will focus on Bonner sphere measurements for our
discussion of few-channel unfolding, and on liquid scintillation spectrometer
(NE213) measurements for our discussion of multi-channel unfolding.
The number
of participants will be restricted due to the limited number of PC-workplaces
available. Therefore, you should register as soon as possible. For on-line
registration and further information please visit the website at: http://www.ptb.de/utc2006/. Contact: Burkhard Wiegel, PTB, email Burkhard.Wiegel@ptb.de The fee for the course is 800 Euro and includes a CD with a
complete set of notes and unfolding software, as well as refreshments.
Radiation Process
Simulation and Modeling User Group
Annual Meeting
The
Radiation Process Simulation and Modeling User Group (RPSMUG) will meet
November 17–18, 2005, in Arlington, Virginia, at the Hilton Garden Inn, Arlington Courthouse
Plaza. The two-day
meeting has two distinct themes: Day 1 is intended for everyone, particularly
individuals interested in process simulation and modeling and how it can be
applied to radiation processing; Day 2 will consist of more detailed
technical presentations. Both days will consist of round-table discussions
and informational sessions related to the use of mathematical models and
simulation in radiation processing (gamma, electron beam, and X-ray). If you
have a topic that you would like discussed, please submit it to questions@rpsmug.org. Watch for
updates and additional information at http://www.rpsmug.org/.
Submitted
by Michael C. Saylor, Special Process Services, L.C.,
703-207-0159 or mcs@his.com
.
The American Nuclear Society Radiation Protection and
Shielding Division Biennial Topical Meeting will be held April 3–6, 2006, at
the Pecos River
Village in Carlsbad, New Mexico.
The conference will open with a keynote address by Dr. Glenn Knoll. Other
outstanding plenary speakers will include Dr. Kenneth Shultis,
Dr. Cassiano de Oliveira and other special speakers.
Workshops will be offered on April 2 and 6, both morning
and afternoon. These continuing education classes with the time and location
are listed in the conference website.
There will be no charge to those registered for the
conference for any of the workshops, although pre-registration is requested.
Attendance at the conference will provide continuing education credits for
various technical certifications depending on the degree of participation by
the attendee.
Tours will be
offered of the Waste Isolation Pilot Plant (WIPP), a licensed and operating
deep geological repository for transuranic waste.
The actual number of visitors WIPP can accommodate will depend on
operational conditions and the work schedule of the facility. The WIPP site
is a federal facility and advance notice will be required for a site visit
so early registration is strongly encouraged.
The Trinity Site is also available to the general public
independent of the conference on Saturday, April 1, 2006. The Trinity Site is
the location of the world’s first detonation of a nuclear weapon.
The call for papers, program and contact information for
the conference can be found at http://www.ans-rpsw-carlsbad.com/.
The Canadian Nuclear Society has
announced that the ANS Reactor Physics Topical PHYSOR-2006, “Advances in
Nuclear Analysis and Simulation,” will be held in Vancouver, BC, Canada, Sept. 10–14, 2006. The
meeting is sponsored by the Reactor Physics Division of the ANS and
co-sponsored by a host of international societies. The conference will be
held at the Hyatt Regency in downtown Vancouver.
You are
invited to visit the meeting website at http://www.cns-snc.ca/physor2006/
to obtain updated information and to download a copy of the call for papers.
The conference chair is Benjamin Rouben, FCNS Manager, Reactor Core Physics
Branch, AECL Sheridan Park (phone 905-823-9060 x 4550, fax: 905-822-0567,
email: roubenb@aecl.ca).
The technical program co-chair is Ken Kozier,
Atomic Energy of Canada Limited (AECL), Chalk River Laboratories, Chalk
River, Ontario, Canada K0J 1J0 (Phone: +1-613-584-8811 + ext.5059, email: physor2006@aecl.ca).
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