Data Bank E-Newsletter November 2009

OECD/NEA Data Bank e-newsletter

No. 6, November 2009

  1. Nuclear data and tools
  2. Processed data libraries
  3. Chemical thermodynamics data
  4. Computer programs
  5. Integral experiments data
  6. Benchmarks and legacy books
  7. Training courses and workshops
  8. Conferences



1. Nuclear data and tools

EXFOR/CINDA – These large databases are maintained and updated by the international Nuclear Reaction Data Centres (NRDC) network, which includes the NEA Data Bank. A large number of EXFOR entries are being revised thanks to the feedback from the Working Party on International Nuclear Data Evaluation Co-operation (WPEC) subgroup 30 on “Improvement of Accessibility and Quality of the EXFOR Database”. In addition, a significant number of entries has been updated with information published in conference proceedings. The data recently published in peer-reviewed journals have been compiled in the following EXFOR entries (this list is limited to new entries from the Data Bank and does not show all recent updates to EXFOR).

Neutron induced reaction
23044 G. Tagliente et al.Experimental study of the 91Zr(n,g) reaction up to 26 keVPhysical Review C 78 (2008) 045804
23049 S.S. Arzumanov et al.Measurement of cross sections for inelastic cold-neutron scattering in metals and polymers by the method of (n,g) analysisPhysics of Atomic Nuclei 71 (2008) 1880
23054  E. Birgersson et al.Properties of the reaction 238U(n,f) at the vibrational resonancesNuclear Physics A 817 (2009) 1
Charged particle induced reaction
o1706 H. Thisgaard et al.Production of the Auger emitter 119Sb for targeted radionuclide therapy using a small PET-cyclotronApplied Radiation and Isotopes 67 (2009) 34
o1708 S. Isaev et al.Proton-induced fission on actinide nuclei at energies 27 and 63 MeVNuclear Physics A 809 (2008) 1
o1709 H. Costantini et al.The 3He(a,g)7Be S-factor at solar energies: The prompt g experiment at LUNANuclear Physics A 814 (2008) 144
o1710 I. Leya et al.Production of noble gas isotopes by proton-induced reactions on bismuthNuclear Instruments and Methods B 266 (2008) 1030
o1713 M. La Cognata et al.Measurement of the 20 and 90 keV Resonances in the 18O(p,a)15N Reaction via the Trojan Horse MethodPhysical Review Letters 101 (2008) 152501
o1714 N. Curtis et al.Search for the a + 6He decay of 10Be via the 16O(18O, 10Be*)24Mg reactionJournal of Physics G 36 (2009) 015108
o1718 C. Fitoussi et al.Measurement of the 24Mg(3He,p)26Al cross section: Implication for 26Al production in the early solar systemPhysical Review C 78 (2008) 044613
o1719 J. Benlliure et al.Production of medium-mass neutron-rich nuclei in reactions induced by 136Xe projectiles at 1 A GeV on a beryllium targetPhysical Review C 78 (2008) 054605
o1724 A.A. Cowley et al.Analyzing power distribution in the 12C(p, pa)8Be(g.s.) reaction at an incident energy of 100 MeVEurophysics Letters 85 (2009) 22001
o1725 Z. 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
o1727 Yu. Titarenko et al.Cross sections for nuclide production in a 56Fe target irradiated by 300, 500, 750, 1000, 1500, and 2600 MeV protons compared with data on a hydrogen target irradiated by 300, 500, 750, 1000, and 1500 MeV/nucleon 56Fe ionsPhysical Review C 78 (2008) 034615
o1729 M. Jaskóla, A Study of Levels in 149Nd Using the (d,p) and (d,t) ReactionsActa Physica Polonica B 39 (2008) 695
o1731 D. Bemmerer et al.Direct measurement of the 15N(p,g)16O total cross section at novae energiesJournal of Physics G 36 (2009) 045202

JEFF – 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. Following the release of JEFF-3.1 in 2005 (see JEFF report 21) and subsequent feedbacks, revisions of part of the neutron-induced library, as well as part of the radioactive decay data and fission yields sub-libraries have been made and released as JEFF-3.1.1. These changes are described in the two following JEFF reports, which have just been published.

JEFF report 20 – The JEFF-3.1/-3.1.1 Radioactive Decay Data and Fission Yields Sub-libraries
This report describes the development, contents and initial validation of the JEFF-3.1 and JEFF-3.1.1 Radioactive Decay Data and Fission Yields Sub-libraries.

JEFF report 22 – The JEFF-3.1.1 Nuclear Data Library
This report provides detailed information on the analysis and incremental validation process that lead to JEFF-3.1.1. The improvements are particularly noteworthy as they pertain to light water reactor applications and the associated fuel cycle.

JANIS – Evaluated libraries have been processed in a consistent way with NJOY to calculate gas production cross sections, KERMA and damage data, as well as thermal neutron scattering cross sections. This includes the processing of some recent libraries, such as JEFF-3.1.1, EAF-2007, JENDL/AC, and TENDL-2008. The JANIS software and database are being upgraded to display these new data. A new webstart version should be available shortly.

WONDER2009 – The 2nd International Workshop on nuclear data evaluation for reactor applications was held in Cadarache, France, from 29 September to 2 October 2009. The main objective of the workshop was to review the current modelling and evaluation methods of nuclear data at low energy and to discuss possible areas of improvements. The workshop was very well attended with more than 70 participants. The presentations are now available online.



2. Processed data libraries

Recently acquired or tested application data libraries:

  • NEA-1847/01 ZZ MATJEFF31.BOLIB, JEFF-3.1 Multigr Coupled(199n + 42gamma) X-Section MATXS Fmt for Nuclear Fission Applications (New)
  • USCD1236/02 ZZ SCALE6.0/COVA-44G, 44-group cross section covariance matrix library extracted from SCALE6.0 (New)


3. Chemical thermodynamics data

The NEA thermochemical database (TDB) and Sorption projects will organise a symposium: Use of RDB and Sorption Models in PA, 17-19 May 2010 at the Akademie Hotel, Karlsruhe, Germany. The objective of this symposium is to present and discuss the principal outcomes of these two projects with interested communities (academic institutions, technical support organisations, waste management organisations, regulatory bodies). Emphasis will be placed on illustrating and discussing the successful use and key challenges when applying thermodynamic models and underlying databases to problems of interest to the waste management community as a whole. To register interest, please send an email to A second announcement with details of the programme and speakers will be available in mid-November 2009.


4. Computer programs

The RADTRAN-3 code system for analysing the radiological impact of the transportation of radioactive materials was previously distributed by the NEA Data Bank as CCC-0508. This version of the code is obsolete and no longer available. The current release, RADTRAN 5.6 bundled with RADCAT 2.3, may be downloaded from Sandia National Laboratories,

The most recently acquired or tested computer codes are:

  • CCC-0754/01 VIM 5.1, Steady-State 3-D Neutron Transport Using ENDF/B or Multigroup Cross Sections (New)
  • CCC-0684/08 NRCDOSE 2.3.13, Evaluation of Routine Radioactive Effluents from Nuclear Power Plants (New)
  • CCC-0522/05 VARSKIN 3 V3.1.0, Dose Calculation for Skin Contamination, with Sadde Input Generator (New)
  • CCC-0760/01 PARTISN 5.97, 1-D, 2-D, 3-D Time-Dependent, Multigroup Deterministic Parallel Neutral Particle Transport Code (New)
  • NEA-1525/16 PENELOPE2008.1, A Code System for Monte-Carlo Simulation of Electron and Photon Transport (New)
  • USCD1238/01 ALICE2008, Particle Spectra from HMS precompound Nucleus Decay (New)
  • NEA-1839/01 ACAB-2008, ACtivation ABacus Code (New)
  • NEA-1840/01 SERPENT 1.1.0, 3-D continuous-energy Monte Carlo reactor physics burnup calculation, lattice physics applications (New)
  • NEA-1833/03 FLUKA2008.3b, Monte Carlo general purpose tool for calculations of particle transport and interactions with matter (New)
  • CCC-0657/01 BETA-S, Multi-Group Beta-Ray Spectra (New)
  • NEA-1846/01 FSKY4C, Gamma Ray Skyshine Analysis 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
Users are requested to download the latest versions when making requests as these forms are regularly updated.

For more details see the daily updated list at


5. Integral experiments data

Criticality Safety
  • The 2009 edition of the International Handbook Criticality Safety Benchmark Evaluation Project (ICSBEP) was released in September. You may request a DVD by accessing the ICSBEP website
Radiation shielding
  • NEA-1517/83 SINBAD-RA-SKYSHINE. Measurements of spatial energy distributions of neutrons and photons scattered in the air near the ground-air interface (skyshine-experiment) (1996-1998) (updated).
Reactor physics
  • The IRPhE annual meeting that took place on 20-22 October 2009 at the NEA led to an extensive discussion of the contents of the 2011 handbook, in which three revisions and nine new evaluations were tentatively approved.
Fuel performance
  • NEA-1776/02 IFPE/PRIMO-BD8, Belgonucléaire and SCK-CEN PRIMO Ramped MOX Fuel Rod BD8 (updated)
  • NEA-1841/01 IFPE/EXP-BDL-406, performance of CANDU natural UO2 fuel (bundles AAH, GF, and XY) irradiated at low linear powers (30-40 kW/m) to burnups above 450 MWh/kgU (AECL-CR) (for FUMEX-III exercise)
Nuclear safety joint research projects
  • CSNI2014/01 OLHF, Sandia Lower Head Failure of the reactor pressure vessel OECD/NEA Project
  • CSNI2004/01 PAKS PROJECT, the fuel behaviour in accident conditions on the basis of analyses of the PAKS-2 event

For more details see



6. Benchmarks and legacy books

  • NEA-1746/04 ZZ PBMR-400, OECD/NEA PBMR Coupled Neutronics/Thermal Hydraulics Transient Benchmark - The PBMR-400 Core Design
  • NEA-1849/01 ZZ PSBT NUPEC PWR Sub-channel Bundle Tests Benchmark
  • NEA-1731/07 ZZ BFBT, OECD/NEA-US/NRC NUPEC BWR Full-size Fine-mesh Bundle Tests Benchmark
  • NEA-1769/03 ZZ UAM-LWR, Uncertainty Analysis in Modelling, Coupled Multi-physics and Multi-scale LWR analysis
  • NEA-1848/02/03 ZZ KALININ3, KALININ-3 Coolant Transient Benchmark
  • NEA-1728/03 IRPhE-HTR-ARCH-01, Archive of HTR Primary Documents
  • NEA-1660/06 IRPHE-SNEAK, KFK SNEAK Fast Reactor Experiments, Primary Documentation


7. Training courses and workshops

  • 9-12 March 2010 - A training course on the Monte Carlo computer code TRIPOLI-4, in co-operation with French Atomic Energy Commission (CEA), will be held at the OECD/NEA Data Bank, Issy-les-Moulineaux, France.
  • 29 March - 2 April 2010 - MCNP/MCNPX Training course, OECD NEA Data Bank - co-sponsored by ORNL/RSICC, Issy-les-Moulineaux, France. Registration form. Syllabus.
  • 6-9 April 2010 -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 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.
  • 3-7 May 2010 - SCALE Criticality Safety and Radiation Shielding Course, OECD/NEA Data Bank - co-sponsored by ORNL/RSICC, Issy-les-Moulineaux, France. Registration form.



8. Conferences

Meetings and conferences sponsored by the Nuclear Science Committee & Data Bank:
  • 26 - 30 April 2010 ND2010: International Conference on Nuclear Data for Science and Technology, Jeju Island, Korea
  • 9 - 14 May 2010 -Physor-2010 Advances in Reactor Physics to Power the Nuclear Renaissance, Sheraton Station Square Hotel, Pittsburgh, PA, USA
  • 17 - 20 October 2010 - Joint Symposium on Supercomputing in Nuclear Applications +Monte-Carlo 2010 Tokyo, SNA2010 + MC 2010, Hitotsubashi Memorial Hall, Tokyo, Japan


See also: Other NEA nuclear science meetings.