The latest version of the Joint Evaluated Fission and Fusion File (JEFF) Evaluated Nuclear Data Library, JEFF-3.1.2, was released in February 2012. It contains a number of data types, including neutron and proton interaction data, radioactive decay data, fission yields and thermal scattering law data. Updates include new hafnium evaluations and more complete gamma-production data for fission products. JEFF-3.1.2 data are available on the NEA website in ENDF-6 neutron library format. The JEFF library combines the efforts of the JEFF, European Fusion Files (EFF) and European Activation Files (EAF) Working Groups to produce a common set of evaluated nuclear data mainly for fission and fusion applications.
The last computer codes, processed data libraries and compiled integral experiments acquired since the last Newsletter are:
|ANISN-ORNL, 1-D Neutron Transport & Gamma Transport in Slab, Cylindrical, Spherical Geometry with Anisotropic Scattering (New)
|CALENDF-2010, Pointwise, Multigroup Neutron Cross-Sections and Probability Tables from ENDF/B Evaluations (New)
|DIF3D10.0, Variational Nodal Methods, Finite Difference Methods to Solve N diffusion & Transport Theory Problems (New)
|EASY-2010, European Neutron Activation System (New)
|ENTREE 1.4.0, BWR Core Simulation System for Space and Time Dependent Coupled Phenomena (Tested)
|FLUKA2011.2.12, Monte Carlo general purpose tool for calculations of particle transport and interactions with matter (Update)
|FSKY4C 1.0, Gamma Ray Skyshine Analysis Code (Tested)
|GEF 2012/2.2, Code for Simulation of Nuclear Fission Process (Update)
|NRCDOSE72 1.2.1, Evaluation of Routine Radioactive Effluents from Nuclear Power Plants with Windows Interface (New)
|REFIT-2009, Multilevel Resonance Parameter Least Square Fit of Neutron Transmission, Capture, Fission & Self Indication Data (Tested)
|RESRAD 6.5, Residual Radioactive Material Guideline Implementation (New)
|SACALC3, Calculates the average solid angle subtended by a volume (New)
|SAPHIRE 7.27, Systems Analysis Programs for Hands-On Integrated Reliability Evaluations (New)
|SCAT-2, Cross Sections and Angular Distributions for Spherical Nuclei by Optical Model (Tested)
|SWORD 4.0, SoftWare for Optimization of Radiation Detectors
|TITAN 1.24, A Three-Dimensional Deterministic Radiation Transport Code System (New)
|U-SHIELDER, Estimates Shielding Thickness of Depleted Uranium for Photons from 0.5 to 10 MeV (New)
|VENTEASY, Criticality Search for a Desired Keffective by Adjusting Dimensions, Nuclide Concentrations, or Buckling (Tested)
|ZZ PIXE2010, Proton/Alpha Ionization (K,L,M shell) Tabulated Cross-Section Library (New)
|ZZ POINT-2009, a Temperature Dependent ENDF/B-VII.0 Cross Section Library (Screened)
|ZZ POINT2011, Linearly Interpolable ENDF/B-VII.1 Beta2 Cross-Section Library for 13 Temperatures (New)
|ZZ VITJEFF311.BOLIB, JEFF-3.1.1 Multi-Group Coupled (199n + 42gamma) Cross-Section Library in AMPX Format for Nuclear Fission Applications (New)
|ZZ VITAMINB7/BUGLEB7, Broad-Grp, Fine-Grp, Coupled N/Gamma Cross-Sec Lib derived from ENDF/B-VII.0 Nuclear Data (Updated)
For more details see the daily updated list at: www.oecd‑nea.org/tools/abstract/new.
Data now available for the following experiments:
Updated data now available for the following experiments:
For further information, please see: www.oecd-nea.org/dbcps/.
The 2011 edition of the International Criticality Safety Benchmark Experiments Project (ICSBEP) is available. The evaluated criticality safety benchmark data are given in nine volumes. These volumes span over 62,000 pages and contain 532 evaluations with benchmark specifications for 4,550 critical, near critical, or subcritical configurations, 24 criticality alarm placement / shielding configurations with multiple dose points for each, and 200 configurations that have been categorised as fundamental physics measurements that are relevant to criticality safety applications. The DVD may be obtained by requesting a copy using the following link: Handbook Request Form.
Mandates for all four of the WPRS Expert Groups have been drafted, reviewed and were approved at the June 2011 Nuclear Science Committee Meeting.
The groups are:
A key activity for each of these groups is to coordinate the development of the Integral Experiments Databases for Fuel Performance (IFPE), Reactor Physics (IRPhE) and Radiation Shielding (SINBAD).
As part of the NEA’s commitment to knowledge management, a new database is under construction based on the data within the International Reactor Physics Experiments Handbook. In conjunction with the creation of the database, a database tool (IDAT) is being developed to facilitate the identification, retrieval and analysis of the information stored in the database. Building on the success of DICE (Database for the International Criticality Safety Benchmark Evaluation Project), the database will incorporate features that allow users to identify experimental information relevant to their particular application.A prototype of the tool will be released in April 2012. The prototype will be tested by a task force established by the IRPhE Technical Review Group and will be demonstrated at various international meetings (e.g. June 2012 ANS meeting in Chicago) over the next 12 months, before general release.
The Expert Group on Uncertainty Analysis has organised a series of workshops on the modeling of transients in LWRs in Karlsruhe, Germany during May 2012. Summary records and copies of workshop presentations are available on the NEA Nuclear Science Website: www.oecd-nea.org/science/wprs/eguam/.
Class sizes are limited and courses may be cancelled if minimum enrollment is not obtained one month prior to course. Course fee is refundable up to one month before each class. After one month, course fee will not be refunded.
Note that all attendees must be registered users.
Updated Information is available at the following page: www.oecd-nea.org/dbcps/training-courses/.