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OECD/NEA Data Bank
Computer Program Service (CPS) E-Newsletter
No. 35, December 2007
Reminder:
Requests for computer codes acquired from RSICC under the new
co-operative arrangement (signed on 10 April, 2006) have to undergo an
additional screening procedure. End-users need to fill in FORMS in order to
obtain a single user/single site license for using such codes. If
you have already downloaded these forms, please note that the
instructions have been updated.
Computer Program Service of the OECD/NEA
Data Bank
Content:
- New computer codes & related
information
- Integral Experiments
- Workshops, training courses &
tutorials,
meetings
The most recently acquired or tested computer
codes
and data libraries are:
| Identification |
Name |
Description |
Computer
Codes and associated Data Libraries
|
| NEA-1209/08 |
DWBA07/DWBB07 |
Elastic scattering with
nucleon-nucleon potential and DWBA for inelastic scattering (New
Version) |
| ESTS1365/01 |
NLCGCS_MPV3.0 |
Inversion of
electromagnetic fields for subsurface electrical properties (New) |
| ESTS0608/01 |
RSAC-6 |
Gamma doses, inhalation
and ingestion doses, fission products inventory after fission products
release (New) |
| CCC-0729/01 |
SERA-1C0 |
Simulation environment for
radiotherapy applications (New) |
| PSR-0482/01 |
REMIT 5.1 |
Radiation exposure
monitoring and information transmittal system (New) |
| PSR-0523/01 |
DEPLETOR V.2 |
Provides depletion
capability to the Purdue Advanced Reactor Core Simulator (PARCS) code
(New) |
| PSR-0533/01 |
SQUIRT 1.1 |
Predicts leakage rate and
crack area for cracked pipes in nuclear power plants (New) |
| CCC-0601/06 |
GENII-LIN-2.1 |
Multipurpose Health
Physics Code (Revised Version) |
| IAEA1379/04 |
PREPRO2007 |
Data Preparation and
Management, Subsidiary Calculations (ENDF Format) (New Version) |
| IAEA0849/15 |
GROUPIE2007 |
Bondarenko Self-Shielded
Cross Sections from ENDF/B (New Version) |
| IAEA1310/11 |
LEGEND2007 |
Angular Distribution Table
Calculations in ENDF Format (New Version) |
| IAEA1311/15 |
LINEAR2007 |
Linear-Linear
Interpolation of ENDF Format Cross-Sections (New Version) |
| IAEA1312/14 |
MERGER2007 |
Merges ENDF/B Data by
Material Number or Identifier (New Version) |
| IAEA0848/17 |
RECENT2007 |
Reconstruction of Cross
Sections Data from Resonance Parameters (New Version) |
| IAEA1314/10 |
RELABEL2007 |
Labels FORTRAN Statements
in ENDF Format Processing Programs (New Version) |
| IAEA0854/15 |
SIGMA1-2007 |
Doppler Broadening ENDF
Format Linear-Linear. Interpolated Point Cross Section (New Version) |
| IAEA1283/06 |
SIXPAK2007 |
ENDF Format Double
Differential Cross Section Converter to Single Differential Format (New
Version) |
| IAEA0932/10 |
VIRGIN2007 |
Calculates Uncollided
Neutron Flux and Neutron Reactions from Transmission in ENDF Format
(New Version) |
| IAEA1380/04 |
ACTIVATE2007 |
Activation Cross Section
by Combining Cross Section and Multiplier (ENDF Fomat) (New Version) |
| IAEA1321/13 |
COMPLOT2007 |
Compare ENDF/B Plots of
Reaction Data (New Version) |
| IAEA1307/14 |
CONVERT2007 |
FORTRAN Program Converter
for Different Computers (New Version) |
| IAEA1308/12 |
DICTIN2007 |
Reaction Index Generated
for ENDF Format (New Version) |
| IAEA1322/16 |
EVALPLOT2007 |
ENDF Plots Cross Section,
Angular Distribution and Energy Distribution (New Version) |
| IAEA1309/11 |
FIXUP2007 |
ENDF Format Redundant
Cross-Sections Check (New Version) |
| IAEA1313/11 |
MIXER2007 |
Cross Sections
Calculations for a Composite Mixture of ENDF Format Material (New
Version) |
| USCD1235/01 |
ENDF-UTILITY-CODES |
Codes to check and
standardize data in the Evaluated Nuclear Data File (ENDF) (New) |
| USCD1208/07 |
CHECKR-7.01 |
ENDF/B Format Check (New
Version) |
| USCD1209/07 |
FIZCON-7.02 |
ENDF/B Cross-Sections
Redundancy Check (New Version) |
| USCD1216/07 |
PSYCHE-7.02 |
ENDF/B Data Consistency
Check in ENDF Format (New Version) |
| USCD1212/07 |
INTER-7.01 |
ENDF/B Thermal
Cross-Sections, Resonance Integrals, G-Factors Calculation (New Version) |
| USCD1218/07 |
STANEF-7.01 |
ENDF/B Book-keeping
Operations for ENDF Format Files (New Version) |
| NEA-0914/07 |
REFIT-2007 |
Multilevel Resonance
Parameter Least Square Fit of Neutron Transmission and Capture Data
(Now Tested) |
| USCD1236/01 |
ZZ-SCALE5.1/COVA-44G |
44-group cross section
covariance matrix library extracted from SCALE5.1 (New) |
| NEA-1730/03 |
ZZ-COV-15GROUP-2006 |
15-group cross section
covariance matrix library (New) |
| NEA-1798/01 |
ANGELO-LAMBDA |
Covariance matrix
interpolation and mathematical verification (New) |
| Integral
Experiments Data |
| NEA-1769/02 |
ZZ-UAM-LWR |
Uncertainty Analysis in
Modelling, Coupled Multi-physics and Multi-scale LWR analysis (New
Edition) - Restricted to participants and authors in UAM-2006 |
| NEA-1731/06 |
ZZ-BFBT |
OECD/NEA-US/NRC NUPEC BWR
Full-size Fine-mesh Bundle Tests Benchmark (New Edition) - Restricted
access |
For
more details see daily updated list
Integral Experiments Data for Model
and Code Validation:
- The 2007 edition of the International Criticality Safety
Benchmark Evaluation Project (ICSBEP)
has been released in
September 2007. It contains now experimental data for over 4092
critical
configurations. Access
to request a copy.
- The International Fuel Performance Experiments Database (IFPE)
contains 1209 cases
(November 2007). Since then new experiments were released in particular
relative to MOX fuels which are in process of being compiled and
evaluated. They shall be integrated into IFPE during 2008.
- The Shielding Benchmark Experiments Database (SINBAD)
includes 42 Reactor Shielding, 27 Fusion Neutronics
Shielding, and 15 Accelerator Shielding Experiments (last update: 21
May 2007).
- The second edition of the International Handbook of
Evaluated Reactor Physics Benchmark Experiments Handbook (IRPhE) was published in March 2007 and
contains reactor physics benchmark specifications that have been
derived from experiments that were performed at various nuclear
experimental facilities around the world. The third edition, including
new evaluations, is scheduled for March 2008.
- Prof. M.M.R
Williams has released the following three of his legacy books
for
free distribution for use by students and other researchers.
- The
Slowing Down and Thermalization of Neutrons, North-Holland
Publishing
Company - Amsterdam, 582 pages, 1966
- Mathematical
Methods in Particle Transport Theory, Butterworths, London, 430
pages,
1971
- Random
Processes in Nuclear Reactors, Pergamon Press Oxford New York
Toronto
Sydney, 243 pages, 1974
- Prof. Jeffery Lewins has recently released the following
two legacy books:
- Importance: The Adjoint Function : The Physical Basis of
Variational and Perturbation Theory in Transport and Diffusion Problems.
- Nuclear Reactor Kinetics and Control
These will be available in the near future on CD-ROM.
Workshops, training courses &
tutorials planned for 2008:
- 30 January - 1 February 2008
Course on "Analytical Benchmarks:
Case Studies in Neutron Transport
Theory" using the Handbook
(including computer codes) to be published on "Analytical Benchmarks
for Nuclear Engineering Applications (Case Studies in Neutron Transport
Theory)". This course is intended for transport methods developers and
those who teach
reactor physics and transport theory. In addition, the course would be
appropriate for anyone with an analytical interest in solving equations
and the application of numerical methods to obtain extreme accuracy
(Registration now closed).
Teacher: Prof. Barry D. Ganapol.
- 25-29
February 2008 Sensitivity
and Uncertainty Analysis Training Course using SCALE TSUNAMI
Syllabus, held at OECD/NEA Headquarters. Registration Form.
- 7-11
April 2008
A training course on the Monte Carlo
computer code
TRIPOLI-4 will be held at OECD/NEA
Headquarters. TRIPOLI-4
Course Programmme. The new version that is being released contains
cross
section libraries from the latest evaluations. It contains also an
interactive pre-processor for preparing of geometries. Registration Form.
- 12-16 May 2008
Joint introductory/intermediate MCNP/MCNPX
training course, ITN,
Sacavem, Lisbon (Portugal) - co-sponsored by
ORNL/RSICC. Registration
form.
- 19-23 May 2008
GEANT4 (a
toolkit for the simulation of the passage of particles
through matter) workshop organised at ORNL by the RSICC
(Radiation Shielding Information Computational Center) in co-operation
with the NEA Data Bank. Programmme,
schedule and additional information.
- 2-6 June 2008
REFIT-2007
Training course - Multilevel
Resonance Parameter Least Square Fit
of Neutron Transmission and Capture Data, EC-JRC-IRMM, Geel,
contact Peter
Schillebeeckx
- 30 June - 3 July 2008
Training course on PENELOPE-2008
- a Code System for Monte Carlo
Simulation of Electron and Photon Transport. Scope & Objectives, Syllabus
and accommodation. Registration
form.
- 29 September - 3 October 2008
Training Course on FLUKA, a
fully integrated particle physics
MonteCarlo simulation package. OECD/NEA Data Bank, Issy les Moulineaux,
France. Registration Form.
- Meetings Sponsored by the Nuclear
Science Committee & Data Bank
2007
- 15-19 April 2007
SNA-2007 +
M&C-2007, Joint International Topical Meeting on Mathematics
& Computation and Supercomputing in Nuclear Applications
Monterey Marriott, Monterey, California, USA
General Chair: Tomas Diaz de la Rubia and Brian Wirth (Lawrence
Livermore National Laboratory)
Technical Program Chair: Jasmina Vujic (University of California,
Berkeley).
- 9-13 September 2007
GLOBAL-2007
Boise, Idaho, USA
Contact: Teri Ehresman
2008
- 13-17 April 2008
Eleventh International Conference
on Radiation
Shielding (ICRS11) and
Fifteenth Topical on Radiation Protection and Shielding (RPS15).
Organiser: Georgia Institute of Technology, Callaway Gardens, Pine
Mountain, Georgia, USA
- 25-30 May 2008
13th
International Symposium on Reactor Dosimetry
Akersloot, Netherlands
2009
- 3-7 May 2009
M&C-2009,
ANS Mathematics and Computation Division (Call for Papers)
Saratoga Springs, NY. USA
Contact: Tom Sutton
- 6-10 September 2009
GLOBAL-2009: 8th
Global Congress on Nuclear Fuel Cycle: Sustainable Options and
Industrial Perspectives, Paris, France
See also: Other
NEA nuclear science meetings
News from the OECD Nuclear Energy Agency (NEA)
The latest issue of the NEA
online bulletin.
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