OECD/NEA Data Bank E-Newsletter

No. 6, November 2009


Contents:
  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 keV, Physical 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) analysis, Physics of Atomic Nuclei 71 (2008) 1880
23054  E. Birgersson et al., Properties of the reaction 238U(n,f) at the vibrational resonances, Nuclear 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-cyclotron, Applied Radiation and Isotopes 67 (2009) 34
o1708 S. Isaev et al., Proton-induced fission on actinide nuclei at energies 27 and 63 MeV, Nuclear 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 LUNA, Nuclear Physics A 814 (2008) 144
o1710 I. Leya et al., Production of noble gas isotopes by proton-induced reactions on bismuth, Nuclear 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 Method, Physical Review Letters 101 (2008) 152501
o1714 N. Curtis et al., Search for the a + 6He decay of 10Be via the 16O(18O, 10Be*)24Mg reaction, Journal 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 system, Physical 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 target, Physical 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 MeV, Europhysics 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 production, Applied 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 ions, Physical Review C 78 (2008) 034615
o1729 M. Jaskóla, A Study of Levels in 149Nd Using the (d,p) and (d,t) Reactions, Acta Physica Polonica B 39 (2008) 695
o1731 D. Bemmerer et al., Direct measurement of the 15N(p,g)16O total cross section at novae energies, Journal of Physics G 36 (2009) 045202

JEFF – The Joint Evaluated Fission and Fusion (JEFF) Project is a collaborative effort among NEA Data Bank member 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 20The 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 22The 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:

For a full list of processed cross-section data libraries visit www.oecd-nea.org/dbprog/categ-z.html.

For the most recent updates to NJOY, a data processing system of evaluated nuclear data files in ENDF format, visit www.oecd-nea.org/dbprog/njoy-links.html.

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 thermodynamicsymposium@oecd-nea.org. 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, https://radtran.sandia.gov.

The most recently acquired or tested computer codes are:

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 www.oecd-nea.org/dbprog/cpsnew.html.


5. Integral experiments data


Criticality Safety
Radiation shielding
Reactor physics
Fuel performance
Nuclear safety joint research projects

For more details see www.oecd-nea.org/dbprog/cpsnew.html.

6. Benchmarks and legacy books

A new Monte Carlo performance benchmark for detailed power density calculations in a full-size reactor core has been announced and is described here. A form to submit the contributions to this benchmark will be available soon.

Information on benchmarks and other legacy books.

7. Training courses and workshops

8. Conferences


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