Data Bank E-Newsletter October 2012

OECD/NEA Data Bank e-newsletter

Issue No. 11, October 2012


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



1. Nuclear data and tools

The NEA Data Bank maintains large databases of bibliographic, experimental and evaluated nuclear data, which are made available to scientists through the NEA website and via the Java-based nuclear information software (JANIS). In June 2012, the NEA released JANIS 3.4 online and on DVD together with the most recent evaluated nuclear data libraries, such as JEFF-3.1.2 and ENDF/B-VII.1. Using the latest version of the software and database, the NEA also made available a compilation of cross-section curves and associated information for neutron-, photon- and light-charged-particle-induced reactions below 200 MeV. This compilation, known as the JANIS Book, provides a global overview of the quality and completeness of experimental and evaluated nuclear data. Find more information on the JANIS web page

The 3rd International Workshop on Nuclear Data Evaluation for Reactor Applications (WONDER 2012), co-organized by the NEA and the CEA Cadarache, was held on 25-28 September 2012 in Aix-en-Provence. More than 50 participants gathered over a 4-day programme to discuss recent results and advances in nuclear data measurements, integral experiments, evaluation of nuclear data and the modelling of the fission process. The presentations are available on the Wonder 2012 home page



2. Computer Program Service

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

Computer programs and processed data libraries:

NEA-1708/06   ADEFTA 4.1, Atomic Densities for Transport Analysis (Tested)
CCC-0793/01   AMP, Advanced Multi-Physics (New)
CCC-0254/12   ANISN-ORNL, 1-D Neutron Transport & Gamma Transport in Slab, Cylindrical, Spherical Geometry with Anisotropic Scattering (Tested)
NEA-1819/01   BURD, Bayesian estimation in data analysis of Probabilistic Safety Assessment (Tested)
NEA-1278/05   CALENDF-2010, Pointwise, Multigroup Neutron Cross-Sections and Probability Tables from ENDF/B Evaluations (Tested)
PSR-0532/02   CEM03.03, Monte-Carlo Code system to calculate nuclear reactions in the framework of the improved cascade-exciton model (New)
USCD1237/01   DRAGON2PARTISN, Cross-Sections Data Generation for PARTISN4.0 (Tested)
NEA-1564/15   EASY-2010, European Neutron Activation System (Update)
NEA-1864/04   GEF, Code for Simulation of Nuclear Fission Process (Update)
CCC-0665/01   HABIT 1.1, Toxic and radioactive release hazards in reactor control room (New)
NEA-1760/04   JANIS 3.4, a Java-based nuclear data display program (New)
PSR-0568/01   PICES, Probabilistic Investigation of Capacity and Energy Shortages (New)
PSR-0573/01   SAEROSA: Single-Species Aerosol Coagulation and Deposition with Arbitrary Size Resolution (New)
CCC-0785/02   SCALE 6.1.1, Modular system for criticality, shielding, source term, fuel depletion/decay, inventories, reactor physics (New)
CCC-0729/02   SERA-1C1, Simulation environment for radiotherapy applications (New)
CCC-0767/03   SWORD 4.0, SoftWare for Optimization of Radiation Detectors (Update)
CCC-0759/05   TITAN 1.29, A Three-Dimensional Deterministic Radiation Transport Code System (New)
USCD-1236/03   ZZ-SCALE6.0/COVA-44G, 44-group cross section covariance matrix library extracted from SCALE6.0 (Update)
DLC-0245/02   ZZ VITAMINB7/BUGLEB7, Broad-Grp, Fine-Grp, Coupled N/Gamma Cross-Sec Lib derived from ENDF/B-VII.0 Nuclear Data (New)
NEA-1870/01   ZZ-VITENDF70.BOLIB, ENDF/B-VII.0 Multi-Grp Coupled (199n +42gamma) AMPX Fmt for Nuclear Fission Applications (New)

Export control and license forms:

For more details see the daily updated list at:



3. Integral experiments data

Nuclear Safety

Data now available for the following experiments:

  • CSNI2006/02 OECD/NEA PRISME Project. The distribution of this package is restricted to participating countries and subject to prior approval.

For more detailed information visit

  • CSNI0080/01 MARVIKEN-ATT, Marviken Aerosol Transport Test experiments.
  • CSNI0078/01 MARVIKEN-FSCB-I, Marviken Full Scale Containment Blowdown experiments Series I.
  • CSNI0079/01 MARVIKEN-FSCB-II, Marviken Full Scale Containment Blowdown experiments Series II.
  • CSNI1001/02 MARVIKEN-CFT, Marviken Full Scale Critical Flow Tests.
  • CSNI1033/01 MARVIKEN-JIT, Marviken Full Scale Jet Impingement Tests experiments.

For more detailed information on the CSNI Code Validation, visit the catalogue

For further information, please see:


Criticality Safety

The 2012 edition of the International Criticality Safety Benchmark Experiments Project (ICSBEP) will be available soon. The evaluated criticality safety benchmark data are given in nine volumes. These volumes span over 65,000 pages and contain 549 evaluations with benchmark specifications for 4,708 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

Integral Experiment Handbooks for Reactor Physics (IRPhE), Radiation Shielding (SINBAD), and Fuel Performance IFPE are being developed under the guidance of NSC Working Party on Scientific Issues of Reactor Systems (WPRS).

The 2012 edition of IRPhE Handbook (DVD) was released in March 2012, containing 52 approved evaluations and four draft evaluations. A prototype of the IRPhE database and analysis tool (IDAT) has been released to a technical review group for testing and will be included in the next edition of the handbook. SINBAD has celebrated the compilation and release of its 100th benchmark. The 11th Workshop on Shielding Aspects of Accelerators, Targets and Irradiation Facilities (SATIF-11) was held at KEK Tsukuba in Japan (September 2012) and its proceedings will be published from NEA, including the current status of SINBAD.



4. Training courses and workshops

Class sizes are limited and courses may be cancelled if minimum enrollment is not obtained one month prior to the course. Course fees paid are refundable up to one month before each class.
Please note that all attendees must be registered users.

  • 14-18 January 2013 - TRIPOLI-4(r), NEA, Paris, France.
  • 04-08 March 2013 - Introduction to MCNP/X using the Visual Editor, NEA, Paris, France.
  • 11-15 March 2013 - MCNP intermediate, NEA, Paris, France.
  • 18-22 March 2013 - Analytical Benchmarks: Case Studies in Neutron Transport Theory, NEA, Paris, France.
  • 27-31 May 2013 - SCALE Criticality Safety Calculations, NEA, Paris, France.
  • 03-07 June 2013 - SCALE Sensitivity and Uncertainty Calculations, NEA, Paris, France


Updated Information is available at the following page:

See also: Other NEA nuclear science meetings.