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Tutorials
All Tutorials are FREE to
registered attendees.
Monte Carlo
TRIPOLI Tutorial
Instructor(s): Yi-Kang Lee,
Jean-Christophe Trama, Stéphane Bourganel,
Maurice Chiron, Cheikh Diop, Eric Dumonteil, Frédéric Laye
Affiliation:
CEA-Saclay, SERMA
Date:
Wednesday, April 16, 2008
Time:
1:30 - 4:30 pm
Summary:
TRIPOLI is the foremost reactor modeling Monte Carlo code in France.
It features continuous-energy physics for neutrons and photons,
advanced and automatic variance reduction strategies, 3D geometry,
full time-dependence and highly parallel operation. It is used
principally for shielding and criticality. TRIPOLI is the major
Monte Carlo design tool for the French nuclear industry, one of the
most advanced nuclear program in the world, and is used for fast
reactors, thermal reactors and advanced nuclear design.
Monte Carlo codes are used more and more worldwide. Thanks to
progress in computing power, more nuclear engineering design will
rely on such codes. As real measurements can be expensive or
impossible, it is important to be able to compare many independent
codes. The developers of TRIPOLI are pleased to present this
outstanding code at the international meeting of ICRS-11 and RPSD
2008.
FLUKA Tutorial
Instructor(s): Stefan Roesler and Markus Brugger
Affiliation:
CERN
Date:
Wednesday, April 16, 2008
Time:
1:30 - 4:30 pm
Summary:
FLUKA
is a fully integrated particle physics Monte Carlo simulation
package. It allows the detailed calculation of hadronic and
electromagnetic cascades in matter including interactions and
transport of heavy ions. FLUKA is used for a wide range of
applications, such as high energy experimental physics, accelerator
and detector design, activation and shielding studies, dosimetry,
cosmic ray studies as well as medical physics and radio-biology.
The
Tutorial gives an overview of the capabilities of the code
illustrated with examples of applications. It will furthermore focus
on the basic steps to run a simulation. They include installation of
the program, the structure of the input file, the creation of
geometries, the main input parameters as well as scoring of physical
quantities and displaying the results. All steps make use of FLAIR,
a user-friendly interface to set up the input file, run FLUKA and
postprocess its output and will be demonstrated online to the
participants.
The
Tutorial addresses users at beginner level and aims at providing the
basic material to run own simple problems. The participants will
receive a CD with the FLUKA package including FLAIR, detailed
documentation and further reading. The lecturers will be available
throughout the conference to provide individual advice for
participants who would like to repeat the examples or run problems
on their own Laptops. Using FLUKA requires Linux as operating system
including the g77 compiler.
Electron/Photon
Transport and Its Applications Tutorial
Instructor(s):
Dr. John C. Garth
Affiliation:
Physicist (retired from
Air Force Research Laboratory, Albuquerque, New Mexico)
Date:
Wednesday, April 16, 2008
Time:
1:30 - 4:30 pm
Summary:
This 3-hour
tutorial will be an introductory survey of the broad field of
coupled electron/photon transport (covering the energy range 10
eV – 30 MeV) and its many applications in radiation physics.
Topics expected to be covered include:
(1) Photon
and electron interaction data,
(2)
Mathematical methods, including Monte Carlo simulation,
transport equation solution, semi-empirical models, and 3-D
transport methods,
(3)
Descriptions of several Monte Carlo codes such as PENELOPE,
EGSnrc, MCNP, and GEANT4 and how they work,
(4)
Electron-beam phenomena such as: backscatter, transmission,
energy and charge deposition, and x-ray generation profiles,
AND,
(5)
Introduction to a wide range of application areas including
(a)
radiation therapy physics,
(b)
treatment planning,
(c)
medical imaging,
(d)
radiation processing,
(e)
radiation biology,
(f)
shielding,
(g)
theoretical and experimental dosimetry, including
dosimetry at material interfaces,
(h)
radiation charging of insulators,
(i)
positron transport,
(j)
x-ray target spectrum prediction
(k)
electron probe microanalysis,
(l)
x-ray fluorescence analysis,
(m)
x-ray photoelectron spectroscopy and Auger electron
spectroscopy,
(n)
secondary electron emission,
(o)
electron slowing down,
(p)
microdosimetry,
(q)
track structure, and
(r)
electron spectroscopies such as EELS, REELS, and EPES.
An electron/photon
transport bibliographic database developed by the author containing
over 4000 references classified under 62 different topic categories
will be described, demonstrated and made available to tutorial
participants. (Participants are encouraged to bring a memory device
to receive electronic copies of the presentation and handouts).
Radiation
Surveys for Therapy Facilities Tutorial
Instructor(s): Nisy Elizabeth Ipe, PhD, CHP
Affiliation:
Consultant, Shielding Design, Dosimetry and Radiation Protection
Date:
Wednesday, April 16, 2008
Time:
1:30 - 3:00 pm
Summary:
Radiation
surveys are required by regulatory agencies during the commissioning
of
therapy
facilities to verify the integrity of the shielding. Therapy linear
accelerators
(linacs)
will be addressed in detail. Brief mention will be made of particle
therapy
facilities
For therapy
linacs while concrete barriers that provide adequate shielding for
photons
also provide
adequate shielding for neutrons, facilities operating at energies
at10 MV and
above shall
be checked for neutrons at the door, maze entrance, and any other
openings
through the
shielding. Laminated barriers shall be monitored for neutrons beyond
the
shielding.
For the primary barrier measurements, the maximum field size is
utilized
without a
phantom in the beam. Gantry angles of 0, 90, 180, 270 degrees as
well oblique
angles
depending upon the shielding configuration are commonly used.
Secondary
barriers are
surveyed with the maximum field size and a phantom in place.
Photon
surveys outside the barriers are performed typically with a
calibrated ionization
chamber
which has both rate and integrate modes, at 30 cm from the barrier.
Head
leakage in
the linac room can be established with the use of film wrapped
around the
linac head
and integrating dosimeters.
In this
tutorial neutron monitoring will be emphasized. Neutron measurements
inside the
treatment
room are fraught with difficulties because of photon interference
from the
primary and
leakage photon beam and the fact that neutron detection is spread
over many
decades of
energy. Thus no single neutron detector can accurately measure
neutron
fluence or
dose equivalent over the entire energy ranges. Additionally neutron
detectors
can have
photon-induced reactions when used in the primary photon beam.
Further
because
therapy linacs are operated in a pulsed mode, the intense photon
pulse
overwhelms
any active detector that detects particles electronically. Thus
active detectors
such as such
as neutron rem-meters, fluence meters and spectrometers neutron
cannot be
used inside
the treatment rooms except at or near the maze entrance. They can be
used
outside the
shielded treatment room.
Passive
monitors with high neutron sensitivity such as moderated activation
foils (gold
and indium)
and threshold activation detectors (phosphorous) can be typically
used inside
the
treatment room and inside the primary beam. Moderated activation
foils can also be
used inside
the treatment room and outside the primary beam. Solid state neutron
detectors (SSNTDs)
such as CR-39 ® and bubble detectors can be used inside the
treatment
room, but outside the primary beam. Bubble detectors can also be
used for
radiation
surveys outside the shielded treatment room.
Unlike
therapy linacs, neutrons are the dominant radiation outside the
shielding for
particle
therapy facilites. Neutron energies can extend to 1 GeV or more for
carbon
therapy
facilities. Some neutron instruments that extend to higher energies
such as Wendi
and Chelsi
are also discussed.
Educational
Objectives:
1.
Understand how to perform shielding integrity radiation surveys
2.
Understand the various neutron monitoring methods and instruments
3.
Understand under which conditions these monitors can be used
SCALE
Tutorial
Instructor(s):
Douglas E. Peplow, John C. Wagner, Stephen M. Bowman
Affiliation:
Oak Ridge National Laboratory
Date:
Friday, April 18, 2008
Time:
9:00 am - 12:00 pm
Summary:
This SCALE
Monte Carlo tutorial session will introduce the new MAVRIC/Monaco
Monte Carlo
sequence with automated 3-D variance reduction using the CADIS
(Consistent
Adjoint
Driven Importance Sampling) methodology. This methodology provides
significant
speedups to
complex shielding problems without requiring user expertise. The
MAVRIC/Monaco
sequence
will be released in October 2008 in SCALE 6. This session is
intended for those who are
interested
in Monte Carlo shielding analysis.
The tutorial
is a 3-hour hands-on demonstration. Simple problems are
described
along with the basics of problem setup. Problems will be run,
geometry displayed with
the KENO3D
visualization tool, and results plotted using a Java-based plotting
program.
Participants
will learn how to to set up and run Monte Carlo shielding
calculations and
plot results
using the popular SCALE code system. Similar workshops at other
national and
international meetings have been popular and successful.
The tutorial
provides the opportunity to become acquainted with a major new
radiation
protection and shielding analysis tool, the SCALE 6 MAVRIC/Monaco
Monte Carlo
sequence.
For possible
updates on this tutorial, participants are encouraged to
pre-register via email to
scalehelp@ornl.gov.
Download SCALE Tutorial Flyer
Monte
Carlo Burnup Tutorial
Instructor(s):
Michael L. Fensin1,2, John S. Hendricks2,
Samim Anghaie1
Affiliation:
1University of Florid Nuclear
and Radiological Engineering Department
2Los Alamos National Laboratory
Date:
Friday, April 18, 2008
Time:
9:00 am - 12:00 pm
Summary:
The
Monte Carlo burnup tutorial session lets participants set up and run
Monte Carlo-linked depletion calculations with MCNPX. It is intended
for those who are familiar with MCNPX and similar codes, or have at
least attended the introductory tutorial.
The
tutorial is a 3-hour hands-on session using either a few provided
laptop computers or the participant’s computer if the code is
obtained in advance from RSICC or OECD/NEA. Simple problems are
described that enable the user to become confident in setting up and
executing depletion calculations with the MCNPX depletion
capability. Capabilities addressed include simple problem setup,
isotope tracking, repeated-structures, and manual isotope
concentration changing.
A
series of simplified Monte Carlo-linked depletion problems will
illustrate the basic capabilities of MCNPX depletion. Topics include
approaches to basic problem set-up, isotope tracking and flux
normalization, repeated structures in burnup, and manual
concentration changes. A previous Monte Carlo Burnup tutorial was
provided at the ANS2007 summer meeting in Boston, MA, and was
popular and successful.
The
Monte Carlo burnup tutorial provides the opportunity to become
acquainted with the Monte Carlo-linked depletion capabilities and
recent MCNPX enhancements by actually setting up and running
illustrative problems.
Moritz
Tutorial
Instructor(s): Kenneth A. Van Riper
Affiliation:
White Rock Science
Date:
Friday, April 18, 2008
Time:
9:00 am - 12:00 pm
Summary:
Moritz is geometry editing and visualization program for
combinatorial geometry used by Monte Carlo transport codes. Although
primarily used with MCNP/MCNPX, Moritz supports other codes such as
TRIPOLI and ITS/ACCEPT. Mesh tallies and particle tracks can be
displayed together with the geometry.
The
Moritz tutorial is intended to give new and prospective users an
overview of available capabilities and features and will introduce
current users to new capabilities. It will provide tips and
techniques for making more effective use of the code for both new
and current users.
Even
though the presenter will be prepared with more than sufficient
presentations to fill the three hour session, dialogue with the
participants is encouraged and will play a major part in determining
which topics are covered in detail. Participants may obtain demo
copies of Moritz (CD or copy from a memory stick) throughout the
conference and at the session. They are invited to discuss any
issues encountered when reading and displaying their models.
Prospective users will learn how Moritz works and its available
features. They and current users will learn how to more effectively
use the code. A similar workshop at RPSD2006 was popular and
successful.
MCBEND
Tutorial
Instructor(s):
Affiliation:
SERCO
Date:
Friday, April 18, 2008
Time:
9:00 am - 12:00 pm
Summary:
MCBEND is a computer program written to solve problems of radiation
transport in sub-critical systems using the Monte Carlo method. It
has evolved through thirty years of continuous development from its
origin as a basic shielding code for simple geometries. It is now
capable of modelling realistic geometries in great detail and is
applicable to an extensive range of problems involving the transport
of neutrons, gamma rays and charged particles.
MCBEND is distributed and
actively supported in use by Serco in UK as part of its ANSWERS
Software Service, with the code development itself being managed by
a collaboration comprising Serco and Sellafield Limited.
This tutorial is aimed at providing a broad understanding of the
capabilities of the code and is a compression of the 4 day
“Introduction to MCBEND” course. The tutorial comprises a mixture
of lectures and demonstrations. Demonstrations will include
constructing MCBEND models for specified problems, checking the
input specifications, displaying the geometry model and performing
full calculations on a PC.
Main Objectives:
• Provide an overview of the MCBEND code
• Familiarisation with the input manual, input style, output files
and method of execution.
• Introduce the geometry modelling package
• Introduce the hole geometry modelling package
• Demonstrate graphics package for displaying and checking geometry
models.
• Explore the source options in MCBEND
• Demonstrate the principal variance reduction techniques of MCBEND.
• Overview of additional features
Topics covered:
• An
overview of the MCBEND code
Execution of an extremely basic problem to
preview the use of the user guide, preparation of input data,
interpretation of output files and the mechanics
of submitting a case for execution.
• The MCBEND Simple Body Geometry Package
A description of the basic components including: simple
bodies; construction of parts; transformations; and boundary
conditions.
• The MCBEND Hole Geometry Package
A description of the hole geometry package including: the
differences between explicit particle tracking and hole tracking;
use of hole materials; transformations; examples of hole materials
• Geometry Data Preparation and Checking
An overview of preparing, specifying and checking geometry
models for MCBEND, including a demonstration of the supporting
graphics package.
• Unified Source options
Specify a source in MCBEND
• Variance reduction.
Manual and automatic creation of importance maps for
accelerating the calculation.
Introduction to MCNPX Tutorial
Instructor(s): John S. Hendricks
Affiliation:
Los Alamos National Laboratory
Date:
Friday, April 18, 2008
Time:
1:00 pm - 4:00 pm
Summary:
The
Monte Carlo tutorial session lets participants set up and run
radiation transport Monte Carlo calculations with MCNPX. It is
intended for those who have never run Monte Carlo or who wish to
become more familiar with the basics of the MCNPX Monte Carlo code.
The
tutorial is a 3-hour hands-on session using either a few provided
laptop computers or the participant’s computer if the code is
obtained in advance from RSICC or OECD/NEA. Simple problems are
described along with the basics of setting them up; then the
participants set up, run and analyze the problems.
Beginning or novice users will be able to set up and run simple
Monte Carlo calculations, becoming both familiar with MCNPX and
similar codes and having first-hand experience with Monte Carlo.
Similar workshops at RPSD2006 national ANS meetings have been
popular and successful.
The
Monte Carlo introductory tutorial provides the opportunity to become
acquainted with a major tool of radiation protection and shielding,
namely the MCNPX Monte Carlo computer code.
NJOY
Tutorial
Instructor(s): A. C. (Skip) Kahler
Affiliation:
Los Alamos National Laboratory
Date:
Friday, April 18, 2008
Time:
1:00 pm - 4:00 pm
Summary:
The
NJOY tutorial session lets participants set up and run the NJOY
Nuclear Data Processing System.
The
tutorial is a 3-hour hands-on session installing and using NJOY.
This
half-day tutorial will provide a brief description and demonstration
of installing and using the NJOY Nuclear Data Processing System.
NJOY can be and has been used in a variety of computing
environments, from large mainframe systems to laptops. This lecture
will be driven from a Windows laptop PC using the freely available
G95 FORTRAN compiler. Sample problems that create continuous energy
(ACE) files necessary for use with the LANL MCNP/MCNPX codes will be
run and the output examined. Jobs using the newly installed ERRORJ
covariance module will also be run and their outputs reviewed. A
limited number of LANL laptop computers will be available for use.
Participants who have already obtained the NJOY99 computer program
package from RSICC or the NEA are encouraged to bring their own
laptops. Discussion by User’s of ongoing and anticipated future
needs is encouraged. No previous experience with the NJOY code
system or the Evaluated Nuclear Data File is assumed.
The
NJOY tutorial provides the opportunity to become acquainted with a
major tool of radiation protection and shielding, namely the NJOY
nuclear data processing computer code.
Attila
Tutorial
Instructor(s): Gregory Failla
Affiliation:
Transpire, Inc.
Date:
Friday, April 18, 2008
Time:
1:00 pm - 4:00 pm
Summary:
Attila is a CAD based deterministic radiation transport software
system which is being used for a broad range of radiation protection
and shielding applications. Attila combines an intuitive, process
based graphical user interface (GUI) with a leading edge solver and
insightful post processing. Attila calculates the angular and energy
dependent flux for all solved particles everywhere in the
computational domain. Response functions such as dose, reaction
rates and user defined quantities can all be calculated through the
GUI as post processing operations. Since Attila is accurate and
efficient through large attenuations, and can import arbitrary CAD
geometries, it is well suited for shielding design applications.
Additionally, Attila can automatically calculate and export
optimized weight windows in a format readable by MCNP/MCNPX,
enabling solutions to be rapidly verified through two independent
first principles solution methods.
The
tutorial will begin with a half hour presentation introducing
Attila, followed by a hands-on workshop where participants will
set-up, analyze, and post process representative shielding
applications.
Participants should bring a laptop with at least 1 GB of RAM
(Windows or Linux Operating System). All participants will be
provided with a 2-week evaluation license of Attila following the
training.
For more information on Attila, please visit
www.transpireinc.com.
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