Data Bank E-Newsletter March 2011

OECD/NEA Data Bank e-newsletter

Issue No. 8, March 2011

Our deep sympathy goes to all those who have suffered as a result of the recent earthquake and tsunami in Japan. Even though we have seen the pictures on our television screens, it is still difficult to truly comprehend how terrible these experiences must have been. We send our very best wishes to all those involved in the rescue, recovery and rebuilding efforts.


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



1. Nuclear data and tools

Experimental Data – The EXFOR database contains experimental data from neutron and charged particle induced reactions. It is maintained by the international network of Nuclear Reaction Data Centres (NRDC), which includes the NEA Data Bank. Data recently published in peer-reviewed journals have been compiled in the following EXFOR entries (this list is limited to new entries from the NEA Data Bank and does not show all recent updates to EXFOR).

22796   M. Mosconi et al.Neutron physics of the Re/Os clock. I. Measurement of the (n,g) cross sections of 186,187,188Os at the CERN n_TOF facilityPhysical Review C 82 (2010) 015802
22822   V. Semkova et al.Neutron activation cross sections for zirconium isotopesNuclear Physics A 832 (2010) 149
22939   I. Dillmann et al.Stellar (n,g) cross sections of p-process isotopes Part I: 102Pd, 120Te, 130,132Ba, and 156DyPhysical Review C 81 (2010) 015801
22994   A. Wallner, Nuclear astrophysics and AMS – Probing nucleosynthesis in the labNuclear Instruments and Methods B 268 (2010) 1277
  S. Vermote et al., Ternary particle emission in spontaneous fission of 250Cf and 252Cf and in neutron induced fission of 249Cf and 251Cf, Nuclear Physics A 837 (2010) 176
23100   A. Letourneau et al.Emission probabilities of g-rays from 238Np and their use for determination of the thermal neutron capture cross section of 237NpApplied Radiation and Isotopes 68 (2010) 432
23027   K. Fujii et al.Neutron physics of the Re/Os clock. III. Resonance analyses and stellar (n,g) cross sections of 186,187,188OsPhysical Review C 82 (2010) 015804
23028   M. Mosconi et al.Neutron physics of the Re/Os clock. II. The (n,n’) cross section of 187Os at 30 keV neutron energyPhysical Review C 82 (2010) 015803
23065   S. Kamada et al.Measurements of keV-Neutron Capture Cross Sections and Capture Gamma-Ray Spectra of 77SeJournal of Nuclear Science and Technology 47 (2010) 634
23067   C. Massimi et al.197Au(n,g) cross section in the resonance regionPhysical Review C 81 (2010) 044616
23076   G. Kessedjian et al.Neutron-induced fission cross sections of short-lived actinides with the surrogate reaction methodPhysics Letters B 692 (2010) 297
23094   J. Marganiec et al.Stellar (n,g) cross sections of p-process isotopes. II. 168Yb, 180W, 184Os, 190Pt, and 196HgPhysical Review C 82 (2010) 035806
23103   T. Wang et al.Measurement of keV-neutron capture cross-sections and capture g-ray spectra of 56Fe and 57FeNuclear Instruments and Methods B 268 (2010) 440
23107   G. Meierhofer et al.Thermal neutron capture cross section of 74GePhysical Review C 81 (2010) 027603
23110   M. Segawa et al.A facility for measurements of (n,g) cross-sections of a nucleus in the range 0.008≤En<20 MeVNuclear Instruments and Methods A 618 (2010) 153
23112   B. L. Goldblum et al.Surrogate ratio methodology for the indirect determination of neutron capture cross sectionsPhysical Review C 81 (2010) 054606
23114   C. Sage et al.High resolution measurements of the 241Am(n,2n) reaction cross sectionPhysical Review C 81 (2010) 064604
23117   G. Tagliente et al.The 92Zr(n,g) reaction and its implications for stellar nucleosynthesisPhysical Review C 81 (2010) 055801
23126   C. Paradela et al.Neutron-induced fission cross section of 234U and 237Np measured at the CERN Neutron Time-of-Flight (n_TOF) facilityPhysical Review C 82 (2010) 034601

Evaluated Data – The Joint Evaluated Fission and Fusion (JEFF) project is a collaborative effort among NEA Data Bank participating countries to compile, maintain and develop a reference nuclear data library for use in different energy applications. Following the adoption by the French nuclear industry of the latest version of the JEFF library (JEFF-3.1.1, released in 2009), the JEFF collaboration efforts now concentrate on the development of its next major release, the JEFF-3.2 library, which will implement more and further improved nuclear data evaluations and is expected for official release in about 2 to 3 year’s time.

The NEA Working Party on International Nuclear Data Evaluation Co-operation (WPEC) provides a worldwide framework for co-operative activities between major nuclear data evaluation projects. Two WPEC subgroups recently completed their work and the final reports are now available. Subgroup 24 was established to develop a methodology for the production of covariance data in the fast neutron region. The report describes the different approaches and compares results obtained with existing nuclear reaction codes. Subgroup 30 focused on improving the accessibility and the quality of the Experimental Nuclear Reaction Data (EXFOR) database. The report describes the translation process from EXFOR into more user-friendly tabulated data files, as well as the various methods developed to verify and correct the contents of the database.



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-0767/01 SWORD 3.2, SoftWare for Optimization of Radiation Detectors (New)
  • NEA-1210/20 ZZ-HATCHES-19, Database for radiochemical modelling (New)
  • NEA-1856/01 VESTA 2.0.3, Monte Carlo depletion interface code (New)
  • CCC-0761/02 RSAC-7.2, Gamma doses, inhalation and ingestion doses, fission products inventory after fission products release (New)
  • CCC-0644/03 HOTSPOT 2.07.1, Field Evaluation of Radiation Release from Nuclear Accident (New)
  • NEA-1857/01 PHITS-2.24, Particle and Heavy Ion Transport code System (New)
  • CCC-0731/01 ORIP-XXI, isotope transmutation simulations (New)
  • CCC-0737/02 GENII 2.10, Environmental Radiation Dosimetry System (New)
  • CCC-0759/03 TITAN 1.21, A Three-Dimensional Deterministic Radiation Transport Code System (New)
  • NEA-1833/05 FLUKA2008.3d, Monte Carlo general purpose tool for calculations of particle transport and interactions with matter (Revised Edition)
  • USCD1238/04 ALICE2010, Particle Spectra from HMS precompound Nucleus Decay (Revised Edition)
  • USCD1239/02 VENTEASY, Criticality search for a desired Keffective by adjusting dimensions, nuclide concentrations, or buckling (Revised Edition)
  • CCC-0684/10 NRCDOSE 2.3.16, Evaluation of Routine Radioactive Effluents from Nuclear Power Plants (New)
  • CCC-0726/02 CNCSN 2009, One, Two- and Three-Dimensional Coupled Neutral and Charged Particle Sn Parallel Multi-Threaded Code System (New)
  • CCC-0768/01 NRCDOSE72 1.1.9, Evaluation of Routine Radioactive Effluents from Nuclear Power Plants with Windows Interface (New)
  • DLC-0236/01 ZZ PHOBIA: Photon Buildup Factors to Account for Angular Incidence on Shield Walls (New)
  • CCC-0774/01 GRSAC, Graphite Reactor Severe Accident Code (New)

Note for users of DVDs sent out by the NEA Data Bank:

The CD-ROM and DVD robot used at the NEA Data Bank to produce copies of the information it distributes has been upgraded. DVDs are produced for large packages with dual layers. The result of this upgrade and modification is that compatibility problems might arise with operating systems and/or DVD-readers older than 12 years, i.e. released before 1997. Users experiencing problems with old DVD readers should either request information on CD-ROM or upgrade their readers.

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:

  • CSNI0073/02 ROSA-IV/SB-CL-27, Large Scale Test Facility, Gravity-Driven Safety Injection
  • CSNI0046/02 ROSA-IV/SB-CL-18, Large Scale Test Facility, 5% Cold-Leg Break Test
  • CSNI0045/02 ROSA-III/984, BWR Rig of Safety Assessment for LOCA, 2.8% Split Break Test
  • CSNI0044/02 ROSA-III/971, BWR Rig of Safety Assessment LOCA, Loss of Offsite Power Transient
  • CSNI0043/02 ROSA-III/952, BWR Rig of Safety Assessment for LOCA, Reference MSL Break Test
  • CSNI0042/02 ROSA-III/926, BWR Rig of Safety Assessment for LOCA, 20% Double-Ended Break
  • CSNI0041/02 ROSA-III/922, BWR Rig of Safety Assessment for LOCA, 5% Split Break Test
  • CSNI0040/02 ROSA-III/916, BWR Rig of Safety Assessment for LOCA, 50% Split Break Test
  • CSNI0039/02 ROSA-III/912, BWR Rig of Safety Assessment for LOCA, 5% Split Break Test

For further information, please see:

Criticality Safety

The 2010 edition of the International Criticality Safety Benchmark Experiments Project (ICSBEP) handbook is now available. The evaluated criticality safety benchmark data are given in nine volumes. These volumes span over 55,000 pages and contain 516 evaluations with benchmark specifications for 4,405 critical, near critical, or subcritical configurations, 24 criticality alarm placement / shielding configurations with multiple dose points for each, and 200 configurations that have been categorized as fundamental physics measurements that are relevant to criticality safety applications.

Reactor Systems

The first meetings of four new Experts Groups under the Working Party on Scientific Issues of Reactor Systems were held at NEA Offices in the first week of February. The groups are:

The roles of EGRFP, EGRTS and EGRPANS will include helping to develop the Integral Experiments Databases IFPESINBAD and IRPhE, respectively. Work has started on reviewing the contents, structure and future requirements of each database. For IRPhE a study is being made on the development of a database tool to allow users to search for experiments of particular interest, similar to the DICE tool already available for ICSBEP. The next issue of the IRPhE handbook is due in April/May 2011.



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 fees are refundable up to one month before each class. After one month, course fees will not be refunded.

Note that all attendees must be registered users.

  • 27 June - 1st July 2011- MCNP/MCNPX Training course, OECD NEA Data Bank - co-sponsored by ORNL/RSICC, University of Barcelona, Barcelona, Spain.
  • 4-7 July 2011 -Training course on PENELOPE 2010 - A code system for Monte Carlo simulation of electron and photon transport, University of Barcelona, Barcelona, Spain.
  • October 2011 - SCALE Sensitivity and Uncertainty Analysis Methods 1D, 2D and 3D sensitivity analysis for eigenvalue and generalized responses. Uncertainty theory and covariance data. Data assimilation (adjustment) methods for code and data validation, OECD NEA Headquarters, Issy-les-Moulineaux, France. Registration not open yet.
  • 7-11 November 2011 - MCNP/MCNPX Training course, OECD NEA Data Bank - co-sponsored by ORNL/RSICC, Imperial College, London, UK.


See also: Other NEA nuclear science meetings.