Data Bank E-Newsletter October 2010

OECD/NEA Data Bank e-newsletter

Issue No. 7, October 2010


  1. Nuclear data and tools
  2. Computer Program Service
  3. Benchmarks
  4. Training courses and workshops
  5. Conferences



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).

Neutron induced reaction


G. Noguère et al.Average neutron parameters for hafniumNuclear Physics A 831 (2009) 106


I. Dillmann et al.Solving the stellar 62Ni problem with AMSNuclear Instruments and Methods B 268 (2010) 1283


H. Harada et al.Measurements of Neutron Capture Cross Section of 237Np for Fast NeutronsJournal of Nuclear Science and Technology 46 (2009) 460


G. Meierhofer et al.Thermal neutron capture cross-section of 76GeEuropean Physical Journal A 40 (2009) 61


M.S. Uddin et al.Measurements of neutron induced activation of concrete at 64.5 MeVAnnals of Nuclear Energy 36 (2009) 1133


F. Atchinson et al.Transmission of very slow neutrons through material foils and its influence on the design of ultracold neutron sourcesNuclear Instruments and Methods A 608 (2009) 144


T. Sanami et al.A Bragg curve counter with an internal production target for the measurement of the double-differential cross-section of fragment production induced by neutrons at energies of tens of MeVNuclear Instruments and Methods A 610 (2009) 660


Charged particle induced reaction


A. Budzanowski et al., Cross section and tensor analysing power of the dd ® h a reaction near thresholdNuclear Physics A 821 (2009) 193


N.I. Ashwood et al.Spectroscopy of 16O using a 12C resonant scattering in inverse kinematics , Journal of Physics G 36 (2009) 055105


M. Mahgoub et al.Role of cross-shell excitations in the reaction 54Fe(d,p) 55FeEuropean Physical Journal A 40 (2009) 35


G. Lhersonneau et al., Neutron yield from carbon, light- and heavy-water thick targets irradiated by 40 MeV deuteronsNuclear Instruments and Methods A 603 (2009) 228


C. Wheldon et al., High-resolution particle spectroscopy of 186ReJournal of Physics G 36 (2009) 095102


J.-L. Lecouey et al.Single-proton removal reaction study of 16BPhysics Letters B 672 (2009) 6


T. Siiskonen et al.Excitation functions for proton-induced reactions on natural hafnium: Production of 177Lu for medical useNuclear Instruments and Methods B 267 (2009) 3500


A. Musumarra et al.Measuring total reaction cross-sections at energies near the coulomb barrier by the active target methodNuclear Instruments and Methods A 612 (2010) 399


S. Pascu et al., Structure investigation with the (p,t) reaction on 132,134Ba nuclei, Physical Review C 81 (2010) 014304


M. Dasgu M. Dasgupta et al.Suppression of fusion by breakup: Resolving the discrepancy between the reactions of 9Be with 208Pb and 209BiPhysical Review C 81 (2010) 024608

Evaluated Data - The Joint Evaluated Fission and Fusion (JEFF) project is a collaborative effort among NEA Data Bank participating countries to develop a reference nuclear data library for use in different energy applications. The JEFF Reports series describe the evaluation and validation of the JEF(F) files from the first version to the latest release (JEFF-3.1.1). The complete collection of JEFF Reports is available on-line and on CD-ROM.

The Working Party on international nuclear data Evaluation Co-operation (WPEC) brings together the world's major evaluation projects in a framework that facilitates the exchange of information and the establishment of co-operative activities within subgroups. The outcome is published in the WPEC Reports series, which are available on-line and on CD-ROM. New subgroups have been recently launched to solve the following issues: Meeting nuclear data needs for advanced reactor systems (Sg31), Evaluation of Pu-239 in the resonance region (Sg34), Scattering angular distribution in the fast energy range (Sg35), and Usage of experimental data for evaluation in the resolved resonance region (Sg36).

Software - The JANIS software is developed by the NEA Data Bank to facilitate the visualisation and manipulation of nuclear data. The new version of the software, JANIS 3.2, allows users to access all major evaluated data libraries, including the latest releases: JENDL-4.0, RUSFOND-2010, CENDL-3.1, TENDL-2009, JEFF-3.1.1, and implements new features to display data uncertainty and their correlation. JANIS can be launched on-line and is also available for download. A DVD version of JANIS 3.2 and its main databases is also available on request and for download.



2. Computer Program Service

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

2.1 Computer programs and processed data libraries

  • USCD1238/03 ALICE2010, Particle Spectra from HMS precompound Nucleus Decay (New)
  • ESTS0219/09 ECO2N, a TOUGH2 fluid property module for mixtures of water-NaCl-CO2 (Tested)
  • ESTS0219/10 TOUGHREACTV1.2, Chemically reactive non-isothermal flows of multiphase fluids in porous and fractured media (New version)
  • IAEA1430/01 ZZ-POINT-2009, a Temperature Dependent ENDF/B-VII.0 Cross Section Library (New)
  • ESTS0608/01 RSAC-6, Gamma doses, inhalation and ingestion doses, fission products inventory after fission products release (New)
  • NEA-1840/02 SERPENT 1.1.7, 3-D continuous-energy Monte Carlo reactor physics burnup calculation, lattice physics applications (New)
  • NEA-1854/01 ZZ-SERPENT117-ACELIB, Continuous-energy X-sec lib., radioactive decay, fission yield data for SERPENT in ACE (New)
  • NEA-1676/07 ERRORJ-2.3, Multigroup covariance matrices generation from ENDF-6 format (Tested)
  • NEA-0549/02/03 STABA, STAGT, Stress Analysis of Dragon HTR Graphite Structure (Tested)
  • NEA-1737/03 TALYS-1.2, computes nuclear reactions cross-sections, yields and spectra via a comprehensive set of nuclear models (New)
  • NEA-0914/08 REFIT-2009, Multilevel Resonance Parameter Least Square Fit of Neutron Transmission, Capture, Fission & Self Indication Data (Tested)
  • CCC-0761/01 RSAC-7, Gamma doses, inhalation and ingestion doses, fission products inventory after fission products release (New)
  • IAEA1432/01 AL-SHIELDER, calculates shielding thickness of aluminum for any photon emitting radionuclide between 0.5 to 10 MeV (Tested)
  • USCD1239/01 VENTEASY, Criticality search for a desired Keffective by adjusting dimensions, nuclide concentrations, or buckling (New)
  • CCC-0759/01 TITAN 1.15, A Three-Dimensional Deterministic Radiation Transport Code System (New)
  • CCC-0755/01 CINDER 1.05, Actinide Transmutation Calculations Code (New)
  • NEA-0829/07 SCAT-2, Cross Sections and Angular Distributions for Spherical Nuclei by Optical Model
  • NEA-1846/02 FSKY4C, Gamma Ray Skyshine Analysis Code (New)
  • NEA-1798/03 ANGELO-LAMBDA, Covariance matrix interpolation and mathematical verification
  • NEA-1833/04 FLUKA2008.3c, Monte Carlo general purpose tool for calculations of particle transport and interactions with matter (New version)
  • IAEA1420/02 ZZ-ADS-LIB/V2.0, test library for Accelerator Driven Systems v.2.0
  • USCS1208/08 CHECKR, ENDF/B Format Check (Tested)
  • USCD1216/08 PSYCHE, ENDF/B Data Consistency Check in ENDF Format
  • USCD1209/08 FIZCON, ENDF/B Cross-Sections Redundancy Check
  • USCD1218/08 STANEF, ENDF/B Book-keeping Operations for ENDF Format Files
  • USCD1235/02 ENDF-UTILITY-CODES, codes to check and standardize data in the Evaluated Nuclear Data File (ENDF)
  • NEA-1852/01 GANDR/SEMOVE, Program for Calculating Derivatives of Processed Multigroup Nuclear Data by Discrete Differences (New)

2.2 Support service to NEA activities

Nuclear Science

  • NEA-1858/01 IFPE/CANDU-FIO-130, CANDU experiment FIO-130 Fuel Behaviour under LOCA Conditions
  • NEA-1697/03 IFPE/HATAC R1, Fission Gas Release at High Burn-up, Effect of a Power Cycling
  • NEA-1553/46 SINBAD-TUD-FE, TUD Iron Slab Experiment
  • NEA-1553/47 SINBAD-TUD-W, TUD/FNG measurement of neutron and photon flux spectra in the FNG tungsten assembly (2002)
  • NEA-1553/48 SINBAD-OKTAVIAN/NI, Osaka Nickel Sphere Benchmark Experiment (OKTAVIAN) (1983)
  • NEA-1553/49 SINBAD-FNG-HCPB, FNG Helium-cooled Pebble Bed (HCPB) Tritium Breeder Module (TBM) Mock-up (2005)
  • NEA-1553/50 SINBAD-OKTAVIAN/FE, Osaka Iron Sphere Benchmark Experiment (OKTAVIAN) (1983)
  • NEA-1553/51 SINBAD-OKTAVIAN/AL, Leakage Neutron and Gamma Spectra from Aluminium Sphere Pile With 14 MeV Neutrons (December 1988)
  • NEA-1553/52 SINBAD-OKTAVIAN/SI, Leakage Neutron and Gamma Spectra from 40 and 60 cm diameter Silicon Sphere Pile With 14 MeV Neutrons (March 1987)
  • NEA-1553/53 SINBAD-OKTAVIAN-W, Leakage Neutron and Gamma Spectra from 40 cm diameter Tungsten Sphere Pile With 14 MeV Neutrons (July 1987)
  • NEA-1849/02/03 ZZ-PSBT, NUPEC PWR Sub-channel Bundle Tests Benchmark

The 2010 edition of the International Reactor Physics Experiments Handbook (IRPhE) was released in June. You may request a DVD by accessing the IRPhE website:

Nuclear Safety

  • CSNI2007/02 STEX-II, International Steam Explosion Experimental Data Base

2.3 Books

  • NEA-1789/02 PMK2-VVER440-REPORTS, Final reports on the PMK-2 projects for VVER Safety Studies

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
Users are requested to download the latest versions when making requests as these forms are regularly updated at
For more details see the daily updated list at



3. Benchmarks

  • Monte Carlo Performance Benchmark for Detailed Power Density Calculations in a Full Size Reactor Core

    The aim of the proposed benchmark test is to monitor over the coming years the (increase in) performance of Monte Carlo calculations of a full size reactor core.
    The ultimate goal is to demonstrate that over time it will become increasingly more practical to calculate a full size reactor core through the Monte Carlo method in a reasonably short time and with sufficient statistical accuracy.
    For further information on how this Benchmark study is structured, its full specifications as well as the kind of results we expect to obtain please refer to:



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.

  • 28 February - 4 March 2011 - MCNP/MCNPX Training course, OECD NEA Data Bank - co-sponsored by ORNL/RSICC, NEA, Issy-les-Moulineaux, France.
  • 7-11 March 2011 - SCALE Lattice Physics and Depletion Training Course, OECD NEA Data Bank - co-sponsored by ORNL/RSICC, NEA, Issy-les-Moulineaux, France.
  • 14-18 March 2011 - Training course on " Analytical Benchmarks: Case Studies in Neutron Transport Theory" using the Handbook (including computer codes) published on "Analytical Benchmarks for Nuclear Engineering Applications (Case Studies in Neutron Transport Theory)". This course, held at the NEA, Issy-les-Moulineaux, France, 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. Teacher: Prof. Barry D. Ganapol.



5. Conferences

Meetings and conferences sponsored by the Nuclear Science Committee & Data Bank:


See also: Other NEA nuclear science meetings.