Data Bank E-Newsletter September 2011

OECD/NEA Data Bank e-newsletter

Issue No. 9, September 2011

On 12 May 2011, the NEA Data Bank welcomed its new Head, Mr. Kiyoshi Matsumoto. Before joining the NEA, he was the General Manager of the Centre for Computational Science and e-Systems at the Japan Atomic Energy Agency (JAEA). Mr. Matsumoto has also worked for Sandia National Laboratory in the United States (specialising in nuclear power plant safety) and the Korean Peninsula Energy Development Organisation (KEDO) in New York.



  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).

Neutron induced reaction



S. Kopecky et al.The total cross section and resonance parameters for the 0.178 eV resonance of 113CdNuclear Instruments and Methods B 267 (2009) 2345



F. Belloni et al. (n_TOF Collaboration), Neutron-induced fission cross-section of 233U in the energy range 0.5 < En < 20MeVEuropean Physical Journal A 47 (2011) 2

Charged particle induced reaction



Z.B. Alfassi et al.On the photon self-absorption correction for thin-target-yields vs. thick-target-yields in radionuclide productionApplied Radiation and Isotopes 67 (2009) 240



M.L. Bonardi et al.Production study of high specific activity NCA 186gRe by proton and deuteron cyclotron irradiationApplied Radiation and Isotopes 68 (2010) 1595Radioanalytical and Nuclear Chemistry 286 (2010) 1



M.S. Uddin et al.Radiochemical determination of cross sections of alpha-particle induced reactions on 192Os for the production of the therapeutic radionuclide 193mPtApplied Radiation and Isotopes 68 (2010) 2001



M. Marta et al.Resonance strengths in the 14N(p,γ)15O and 15N(p,αγ)12C reactionsPhysical Review C 81 (2010) 055807



H.K. Toft et al.Level densities and γ-ray strength functions in Sn isotopesPhysical Review C 81 (2010) 064311



S. Dymov et al.Deuteron breakup pd{pp}sn with forward emission of a fast 1S0 diprotonPhysical Review C 81 (2010) 044001



B. Limata et al. (LUNA Collaboration), New experimental study of low-energy (p,γ) resonances in magnesium isotopesPhysical Review C 82 (2010) 015801



C. Rodriguez-Tajes et al.One-neutron knockout from light neutron-rich nuclei at relativistic energiesPhysical Review C 82 (2010) 024305



A. Di Pietro et al.Elastic scattering and reaction mechanisms of the Halo nucleus 11Be around the Coulomb barrierPhysical Review Letters 105 (2010) 022701



A. Heusler et al.Observation of five high-spin members of the g9/2 f7/2 multiplet in 208PbEuropean Physical Journal A 44 (2010) 233



A. Heusler et al.Observation of the 2- state in 208Pb with a major s1/2 p3/2 structure and structure of ten more 2- statesEuropean Physical Journal A 46 (2010) 17



H. Mardanpour et al.Spin-isospin selectivity in three-nucleon forcesPhysics Letters B 687 (2010) 149



M.L. Sergi et al.New high accuracy measurement of the 17O(p,α)14N reaction rate at astrophysical temperaturesPhysical Review C 82 (2010) 032801



A. Budzanowski et al.Comparison of nonequilibrium processes in p + Ni and p + Au collisions at GeV energiesPhysical Review C 82 (2010) 034605



A. Budzanowski et al. (COSY-GEM Collaboration), Experimental study of the p+6Liη+7Be reaction 11.3 MeV above thresholdPhysical Review C 82 (2010) 041001



A. Lemasson et al.Reactions with the double-Borromean nucleus 8HePhysical Review C 82 (2010) 044617



G. Suliman et al.Study of the 131Ba nucleus with the (d,t) reactionEuropean Physical Journal A 46 (2010) 187



M. Kokkoris et al.Differential cross sections for the 11B(p,α0)8Be and 11B(p,p0)11B reactions, suitable for ion beam analysisNuclear Instruments and Methods B 268 (2010) 3539



S. Manenti et al.Excitation function for deuteron induced nuclear reactions on natural ytterbium for production of high specific activity 177gLu in no-carrier-added form for metabolic radiotherapyApplied Radiation and Isotopes 69 (2011) 37



L. Joulaeizadeh et al.Pionic fusion in light-ion systemsPhysics Letters B 694 (2011) 310



M.L. Bonardi et al.Excitation functions and yields for cyclotron production of radiorhenium via natW(p,xn)181-186gRe nuclear reactions and tests on the production of 186gRe using enriched 186WRadiochimica Acta 99 (2011) 1



W. von Oertzen et al.Shell model and band structures in 19OEuropean Physical Journal A 46 (2010) 345



K. Wimmer et al.Discovery of the shape coexisting 0+ state in 32Mg by a two neutron transfer reactionPhysical Review Letters 105 (2010) 252501



W. von Oertzen et al.Molecular and cluster structures in 18OEuropean Physical Journal A 43 (2010) 17



P. Granholm et al.On the decay of the Jπ= 11/2-, T1/2 = 38.9 h isomer in 133Ba: search for the E5 transition and verification of the EC branchJournal of Physics G 38 (2011) 015101



M.M. Shehata et al.Separation of radioarsenic from irradiated germanium oxide targets for the production of 71As and 72AsRadioanalytical and Nuclear Chemistry 287 (2011) 435

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. Currently, the JEFF collaboration efforts are focused on the development of its next major release, the JEFF-3.2 library, which will implement more and further improved nuclear data, including new actinide evaluations. JEFF-3.2 is expected for official release in 2013. In preparation of this release a starter library, JEFF-3.2T1 was distributed in May 2011 and is currently being tested. A shorter-term release will be a minor update of the JEFF.3.1.1 library, which will be named JEFF-3.1.2 and is expected in the fall of 2011.

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. New reports were recently published by two Working Party subgroups.
Subgroup 32 (SG32) was established to assess the methodologies used in the unresolved resonance region for cross-section and covariance representation. The final SG32 report describes investigations made on the use of the single-level Breit-Wigner formalism in this energy region and recommends improving the cross-section and covariance representation in the ENDF format. WPEC Subgroup 33 (SG33) studies methods and issues in the combined use of integral experiments and covariance data with the objective of recommending a set of best and consistent practices in order to improve evaluated nuclear data files. The intermediate SG33 report reviews and assesses the existing nuclear data adjustment methodologies.



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

  • NEA-1839/02 ACAB-2008, ACtivation ABacus Code (Tested)
  • IAEA1380/05 ACTIVATE2010, Activation Cross Section by Combining Cross Section and Multiplier (ENDF Format) (New)
  • USCD1238/05 ALICE2011, Particle Spectra from HMS precompound Nucleus Decay (Tested)
  • CCC-0777/01 COG 11, Multiparticle Monte Carlo Code System for Shielding and Criticality Use (New)
  • IAEA1321/14 COMPLOT2010, Compare ENDF/B Plots of Reaction Data (New)
  • IAEA1307/15 CONVERT2010, FORTRAN Program Converter for Different Computers (New)
  • IAEA1308/13 DICTIN2010, Reaction Index Generated for ENDF Format (New)
  • USCD1234/01 DRAGON 3.05D, Reactor Cell Calculation System with Burnup (Tested)
  • CCC-0295/01 ELGATL, Calculation of Energy Spectra from Coupled Electron-Photon Slowing Down (New)
  • IAEA1322/17 EVALPLOT2010, ENDF Plots Cross Section, Angular Distribution and Energy Distribution (New)
  • PSR-0563/01 FEAST-METAL-V.1.0, Fuel Engineering and Structural analysis Tool (New)
  • NEA-1080/10FEMAXI-6 VER.1(U), Thermal and Mechanical Behaviour of LWR Fuel Rods (Tested)
  • IAEA1309/12 FIXUP2010, ENDF Format Redundant Cross-Sections Check (New)
  • IAEA0849/16 GROUPIE2010, Bondarenko Self-Shielded Cross Sections from ENDF/B (New)
  • NEA-1838/01 JASMINE V.3, Steam explosion simulation (New)
  • NEA-1865/01 KICHE 1.3, Kinetics of Iodine Chemistry in the Containment of LWRs under Severe Accident Conditions (New)
  • IAEA1310/12 LEGEND2010, Angular Distribution Table Calculations in ENDF Format (New)
  • IAEA1311/16 LINEAR2010, Linear-Linear Interpolation of ENDF Format Cross-Sections (New)
  • IAEA1312/15 MERGER2010, Merges ENDF/B Data by Material Number or Identifier (New)
  • IAEA1313/12 MIXER2010, Cross Sections Calculations for a Composite Mixture of ENDF Format Material (New)
  • NEA-1525/18 PENELOPE2011, A Code System for Monte-Carlo Simulation of Electron and Photon Transport (New)
  • NEA-1857/01 PHITS-2.24, Particle and Heavy Ion Transport code System (Tested)
  • IAEA1379/05 PREPRO2010, Data Preparation and Management, Subsidiary Calculations (ENDF Format) (New)
  • IAEA0848/18 RECENT2010, Reconstruction of Cross Sections Data from Resonance Parameters (New)
  • NEA-1867/01 RAPID, RAdial power and burnup Prediction by following fissile Isotope Distribution in the pellet (New)
  • IAEA1314/11 RELABEL2010, Labels FORTRAN Statements in ENDF Format Processing Programs (New)
  • CCC-0785/01 SCALE 6.1, Modular system for criticality, shielding, source term, fuel depletion/decay, inventories, reactor physics (New)
  • IAEA1287/01 SHIELD, Monte-Carlo Code for Simulating Interaction of High Energy Hadrons with Complex Macroscopic Targets (Tested)
  • IAEA0854/16 SIGMA1-2010, Doppler Broadening ENDF Format Linear-Linear. Interpolated Point Cross Section (New)
  • IAEA1283/07 SIXPAK2010, ENDF Format Double Differential Cross Section Converter to Single Differential Format (New)
  • IAEA1433/01 SPECTRA2010, Convert model and general tabulation to linearized spectra (MF=5) (New)
  • IAEA1382/03 SRNA-2K5, Proton Transport Using 3-D by Monte Carlo Techniques (Tested)
  • IAEA0970/01 STOPOW, Stopping Power of Fast Ions in Matter (Tested)
  • CCC-0781/01 VARSKIN 4 V4.0.0, Dose Calculation for Skin Contamination, with Sadde Input Generator (New)
  • USCD1240/01 VIM_NC, VIM color syntax for Nuclear Codes: NJOY, DRAGON, PARTISN, TORT, MONK, and MCNP (New)
  • IAEA0932/11 VIRGIN2010, Calculates Uncollided Neutron Flux and Neutron Reactions from Transmission in ENDF Format (New)
  • NEA-1866/01 ZZ BUGJEFF311.BOLIB, JEFF-3.1.1 Broad-Group Coupled X Sect Lib. for LWR Shielding & Pressure Vessel Dosimetry 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:

  • CSNI2017/01 MCCI-2 PROJECT, Melt Coolability and Concrete Interaction Phase 2 Project

For further information, please see:

Criticality Safety

The 2011 edition of the International Criticality Safety Benchmark Experiments Project (ICSBEP) handbook will be available shortly. The evaluated criticality safety benchmark data are given in nine volumes. These volumes span over 58,000 pages and contain 533 evaluations with benchmark specifications for 4,551 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 via the Idaho National Laboratory website.

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 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. As in DICE, the user will be able to query based on parameters such geometry as well as calculated quantities, for instance, reactor spectrum and reaction rates. Currently the design specifications of the database and tool have been drafted, and a prototype is planned for demonstration at the October 2011 IRPhE meeting.

The 2011 version of the IRPhE Handbook was published in June 2011. The Handbook can be requested by accessing the corresponding IRPhEP web pages filling in the REQUEST FORM. It is distributed on DVD. The IRPhEP Handbook is available to authorised requesters from the OECD member countries and to contributing establishments from non-OECD countries. Other requests are handled on a case by case basis.

The Expert Group on Uncertainty Analysis has organised a series of workshops on the modeling of transients in LWRs in Stockholm during May 2011. 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 enrolment 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.

  • 7-11 November 2011 - MCNP/MCNPX Training course, OECD NEA Data Bank - co-sponsored by ORNL/RSICC, Imperial College, London, UK.
  • 20-24 February 2012 - Introduction to MCNP/MCNPX using the MCNPX Visual Editor.
  • 27 February to - March 2012 - MCNP intermediate Training Course.
  • 5-9 March 2012 - 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.

Updated information is available at the following page:

See also: Other NEA nuclear science meetings.