Data Bank E-Newsletter March 2012

OECD/NEA Data Bank e-newsletter

Issue No. 10, March 2012


  1. Nuclear data and tools
  2. Computer Program Service
  3. Integral experiments data
  4. Training courses and workshops



1. Nuclear data and tools

JEFF-3.1.2 Nuclear Data Library released

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.



2. Computer Program Service

The last computer codes, processed data libraries and compiled integral experiments acquired since the last Newsletter are:


Computer programs and processed data libraries:

CCC-0254/12   ANISN-ORNL, 1-D Neutron Transport & Gamma Transport in Slab, Cylindrical, Spherical Geometry with Anisotropic Scattering (New)
NEA-1278/05   CALENDF-2010, Pointwise, Multigroup Neutron Cross-Sections and Probability Tables from ENDF/B Evaluations (New)
CCC-0784/01   DIF3D10.0, Variational Nodal Methods, Finite Difference Methods to Solve N diffusion & Transport Theory Problems (New)
NEA-1564/13/14   EASY-2010, European Neutron Activation System (New)
NEA-1686/01   ENTREE 1.4.0, BWR Core Simulation System for Space and Time Dependent Coupled Phenomena (Tested)
NEA-1833/07   FLUKA2011.2.12, Monte Carlo general purpose tool for calculations of particle transport and interactions with matter (Update)
NEA-1846/02   FSKY4C 1.0, Gamma Ray Skyshine Analysis Code (Tested)
NEA-1864/03   GEF 2012/2.2, Code for Simulation of Nuclear Fission Process (Update)
CCC-0768/02   NRCDOSE72 1.2.1, Evaluation of Routine Radioactive Effluents from Nuclear Power Plants with Windows Interface (New)
NEA-0914/08   REFIT-2009, Multilevel Resonance Parameter Least Square Fit of Neutron Transmission, Capture, Fission & Self Indication Data (Tested)
CCC-0786/01   RESRAD 6.5, Residual Radioactive Material Guideline Implementation (New)
NEA-1688/01   SACALC3, Calculates the average solid angle subtended by a volume (New)
PSR-0405/03   SAPHIRE 7.27, Systems Analysis Programs for Hands-On Integrated Reliability Evaluations (New)
NEA-0829/07   SCAT-2, Cross Sections and Angular Distributions for Spherical Nuclei by Optical Model (Tested)
CCC-0767/02   SWORD 4.0, SoftWare for Optimization of Radiation Detectors
CCC-0759/04   TITAN 1.24, A Three-Dimensional Deterministic Radiation Transport Code System (New)
IAEA1434/01   U-SHIELDER, Estimates Shielding Thickness of Depleted Uranium for Photons from 0.5 to 10 MeV (New)
USCD1239/02   VENTEASY, Criticality Search for a Desired Keffective by Adjusting Dimensions, Nuclide Concentrations, or Buckling (Tested)
NEA-1868/01   ZZ PIXE2010, Proton/Alpha Ionization (K,L,M shell) Tabulated Cross-Section Library (New)
IAEA1430/01   ZZ POINT-2009, a Temperature Dependent ENDF/B-VII.0 Cross Section Library (Screened)
DLC-0247/01   ZZ POINT2011, Linearly Interpolable ENDF/B-VII.1 Beta2 Cross-Section Library for 13 Temperatures (New)
NEA-1869/01   ZZ VITJEFF311.BOLIB, JEFF-3.1.1 Multi-Group Coupled (199n + 42gamma) Cross-Section Library in AMPX Format for Nuclear Fission Applications (New)
DLC-0245/02   ZZ VITAMINB7/BUGLEB7, Broad-Grp, Fine-Grp, Coupled N/Gamma Cross-Sec Lib derived from ENDF/B-VII.0 Nuclear Data (Updated)

Export control and license forms:

For more details see the daily updated list at: www.oecd‑



3. Integral experiments data

Nuclear Safety

Data now available for the following experiments:

  • CSNI2018/01 BIP, OECD/NEA Behaviour of Iodine Project
  • CSNI2019/01 SCIP, OECD/NEA Studsvik Cladding Integrity Project
  • CSNI2020/01 SETH-2, OECD/NEA SESAR Thermal-hydraulics Project

Updated data now available for the following experiments:

  • NEA-1778/02 IFPE/IFA-514/565, LWR MOX Fuel Irradiation Tests
  • NEA-1848/04 KALININ-3 Coolant Transient Benchmark Proceedings
  • NEA-1849/04 NUPEC PWR Sub-channel Bundle Tests Benchmark Proceedings
  • NEA-1849/05 NUPEC PWR Sub-channel Bundle Tests Benchmark Specifications
  • NEA-1769/04 Uncertainty Analysis in Modelling, Coupled Multi-physics and Multi-scale LWR analysis Proceedings
  • NEA-1693/07 VVER-1000 coolant transient (V1000CT) Benchmark Proceedings
  • NEA-1553/54 SINBAD-FNG-BLKT, FNG Neutronics Bulk SS Shield Experiment
  • NEA-1553/55 SINBAD-FNG-DOSE-RATE, FNG-ITER Dose Rate Experiment
  • NEA-1553/56 SINBAD-FNG-SIC, FNG Benchmark Experiment on Silicon Carbide
  • NEA-1553/57 SINBAD-FNG-SS, SS Bulk Shield Benchmark Experiment at FNG/ENEA, FENDL Benchmark for IAEA/NDS
  • NEA-1553/58 SINBAD-FNG-STREAMING, FNG-ITER Neutron Streaming Experiment
  • NEA-1553/59 SINBAD-FNG-W, FNG Benchmark Experiment on Tungsten
  • NEA-1553/60 SINBAD-FNS-DUCT, Dogleg Duct Streaming Experiment with 14 MeV Neutron Source
  • NEA-1553/61 SINBAD-FNS-OXYGEN, FNS/JAERI Time-of-Flight Experiment on Liquid Oxygen Slab With 14 MeV D-T Neutrons
  • NEA-1553/62 SINBAD-FNS-SKYSHINE, FNS/JAERI Measurement of Radiation Skyshine with D-T Neutron Source
  • NEA-1553/69 SINBAD-TUD-FNG-BS, TUD/FNG Measurement of Neutron and Photon Spectra in an ITER Bulk Shield Mock-up
  • NEA-1553/70 SINBAD-TUD-FNG-SIC, TUD/FNG measurement of neutron and photon flux spectra in a silicon carbide assembly
  • NEA-1553/71 SINBAD-FNG-HCPB, FNG Helium-cooled Pebble Bed (HCPB) Tritium Breeder Module (TBM) Mock-up
  • NEA-1553/72 SINBAD-FNS-C-CYLIND, Integral Experiment on a 60 cm-thick Graphite Cylindrical Assembly
  • NEA-1553/73 SINBAD-FNS-V, Neutron spectra and dosimetry, gamma-ray spectra and heating from a 25.4 cm cube of Vanadium irradiated with a D-T neutron source
  • NEA-1553/74 SINBAD-FNS-W, FNS/JAERI Clean Benchmark Experiment on Tungsten Cylindrical Assembly
  • NEA-1553/75 SINBAD-IPPE-FE, IPPE neutron transmission benchmark experiment with 14 MeV neutrons through iron shells
  • NEA-1553/76 SINBAD-IPPE-V, IPPE neutron transmission benchmark experiment with 14 MeV neutrons through vanadium shells
  • NEA-1553/77 SINBAD-OKTAVIAN/AL, Leakage Neutron and Gamma Spectra from Aluminium Sphere Pile With 14 MeV Neutrons
  • NEA-1553/78 SINBAD-OKTAVIAN/MN, Leakage Neutron and Gamma Spectra from 60 cm diameter Manganese Sphere. Pile With 14 MeV Neutrons
  • NEA-1552/34 SINBAD-52P, Transmission Through Shielding Materials of Neutrons and Photons Generated by 52 MeV Protons
  • NEA-1552/35 SINBAD-HIMAC, HIMAC experiments stopping He, C, Ne, Ar, Xe, Fe & Si ions on Al, C, Cu & Pb targets
  • NEA-1552/36 SINBAD-HIMAC800-CONC, Measurements of high energy neutrons (up to 800 MeV) penetrated through concrete shields (HIMAC/NIRS)
  • NEA-1552/37 SINBAD-HIMAC800-FE, Measurements of high energy neutrons (up to 800 MeV) penetrated through iron shields (HIMAC/NIRS)
  • NEA-1552/38 SINBAD-ISIS800, ISIS Benchmark Experiment on Deep-Penetration Neutrons through Concrete and Iron Shields
  • NEA-1552/39 SINBAD-MSU/155 HE-C, MSU experiment stopping 155 Mev /nucleon He and C ions on aluminum target
  • NEA-1517/86 SINBAD-NAIADE-CONC, 60cm Fission Concrete Benchmarks in NAIADE 1 followed by pure thermal neutron benchmarks in light water and in concrete.
  • NEA-1517/87 SINBAD-IPPE-BIS, IPPE neutron transmission benchmark experiment with 14 MeV and Cf-252 fission neutrons through bismuth shell
  • NEA-1517/88 SINBAD-IPPE-TH, IPPE neutron transmission benchmark experiment with 14 MeV and Cf-252 fission neutrons through thorium shell

For further information, please see:


Criticality Safety

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.

Reactor Systems

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:



4. Training courses and workshops

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.

  • 21-25 May 2012 - SCALE6 Lattice Physics and Depletion Course, NEA, Paris, France
  • 2-6 July 2012 - MCNP intermediate, University of Barcelona, Spain
  • 9-12 July 2012 - PENELOPE-2011 Training Course, University of Barcelona, Spain
  • 8-12 October 2012 - TRIPOLI-4, NEA, Paris, France

Updated Information is available at the following page:


See also: other NEA nuclear science meetings.