Advertisement

Nuclear Data Libraries

  • Yican Wu
Chapter

Abstract

The neutronics simulation of nuclear systems relies on the availability of nuclear data to provide accurate numerical representation of the underlying physical processes. Essential nuclear data include energy-dependent reaction cross sections, the energy, and angular distributions of reaction products for various combinations of incident particles and targets, and the atomic and nuclear properties of excited states as well as their radioactive decay data. Nuclear data are the foundation of both nuclear science and technology research and nuclear engineering design. Advanced nuclear systems have the characteristics of complex neutron spectra and angular distribution, complex material composition, and extreme multi-physics coupling. These issues place higher requirements on the accuracy, the width of the energy region, and the species of nuclides for nuclear data.

References

  1. 1.
    Otuka N, Dupont E, Semkova V et al (2014) Towards a more complete and accurate experimental nuclear reaction data library (EXFOR): international collaboration between nuclear reaction data centers (NRDC). Nucl Data Sheets 120:272–276CrossRefGoogle Scholar
  2. 2.
    Ge ZG, Chen YJ (2015) Status and prospects of nuclear data development in China. China Sci Bull 60(3087):3098 (in Chinese)Google Scholar
  3. 3.
    Chadwick MB, Obložinský P, Herman M et al (2006) ENDF/B-VII. 0: next generation evaluated nuclear data library for nuclear science and technology. Nucl Data Sheets 107(12):2931–3060Google Scholar
  4. 4.
    Zhigang G, Hongwei Y, Youxiang Z et al (2007) The updated version of the Chinese evaluated nuclear data library (CENDL-3.1) and China nuclear data evaluation activities. In: International conference on nuclear data for science and technology. EDP SciencesGoogle Scholar
  5. 5.
    Santamarina A, Bernard D, Blaise P et al (2009) The JEFF-3.1. 1 nuclear data library. JEFF report 22(10.2):2Google Scholar
  6. 6.
    Shibata K, Kawano T, Nakagawa T et al (2002) Japanese evaluated nuclear data library version 3 revision-3: JENDL-3.3. J Nucl Sci Technol 39(11):1125–1136Google Scholar
  7. 7.
    Lemmel HD, McLaughlin PK (1944) BROND-2.2 Russian evaluated neutron reaction data library. International Atomic Energy AgencyGoogle Scholar
  8. 8.
    Lopez Aldama D, Trkov A (2004) FENDL-2.1: update of an evaluated nuclear data library for fusion applications. International Atomic Energy AgencyGoogle Scholar
  9. 9.
    Aldama DL, Leszczynski F, Trkov A (2003) WIMS-D library update. Final report of a co-ordinate research projectGoogle Scholar
  10. 10.
    Forrest RA, Kopecky J, Sublet JC (2007) The European transmutation file: EAF-2007 neutron-induced cross section libraries. EURATOM/UKAEA Fusion AssociationGoogle Scholar
  11. 11.
    Jordan WC, Bowman SM, Hollenbach DF (1997) Scale cross-section libraries. Vol. III, Sect. M4 of SCALE: a modular code system for performing standardized computer analysis for licensing evaluation. NUREG/CR-0200 Rev 7(3)Google Scholar
  12. 12.
    Shimakawa S, Sekimura N, Nojiri N (2003) Radiation damage calculation by NPRIM computer code with JENDL3.3. Department of HTTR Project, Japan Atomic Energy research InstituteGoogle Scholar
  13. 13.
    Greenwood LR, Smither RK (2002) SPECTER: neutron damage calculations for materials irradiations. Los Alamos National LaboratoryGoogle Scholar
  14. 14.
    Zou J, Zeng Q, Chen C (2013) Development and application of HENDL-ADS/MG cross section library for ADS system. Am Nucl Soc 108:883–886Google Scholar
  15. 15.
    Zou J, Zeng Q, Xu D et al (2012) Design and producing of fine-group cross section library HENDL3.0/FG for subcritical systemGoogle Scholar
  16. 16.
    Dezheng X, Jieqiong J, Jun Z et al (2009) Integral numerical test of the hybrid evaluated nuclear data library HENDL2.0 for heavy nuclides. Chin J Nucl Sci Eng 29(1):71–75Google Scholar
  17. 17.
    Xu D, He Z, Zou J et al (2010) Production and testing of HENDL-2.1/CG coarse-group cross-section library based on ENDF/B-VII. 0. Fusion Eng Des 85(10):2105–2110Google Scholar
  18. 18.
    MacFarlane RE, Muir DW (1994) The NJOY nuclear data processing system, version 91 (Vol. 7). Los Alamos, NM. LA-12740-MGoogle Scholar
  19. 19.
    Xie ZS, Deng L (2005) Numerical calculation method of neutron transport theory. Northwestern Polytechnical University Press (in Chinese)Google Scholar
  20. 20.
    Ding DZ, Ye CHT, Zhao ZH X et al (2003) Neutron physics-theory, methods, application. Atomic Energy Press (in Chinese)Google Scholar
  21. 21.
    Sun MP (2015) Development and test of fine group nuclear database for advanced nuclear systems. University of Science and Technology of China (in Chinese)Google Scholar
  22. 22.
    Forres RA, Gilbert MR (2007) FISPACT-2007: user manual. EURATOM/UKAEA fusion associationGoogle Scholar
  23. 23.
    Wang RF (1993) Radiation damage of metallic material. Science Press (in Chinese)Google Scholar
  24. 24.
    Odette GR, Doiron DR (1976) Neutron-energy-dependent defect production cross sections for fission and fusion applications. Nucl Technol 29(3):346–368Google Scholar
  25. 25.
    Zou J, He Z, Zeng Q et al (2010) Development and testing of multigroup library with correction of self-shielding effects in fusion–fission hybrid reactor. Fusion Eng Des 85(7):1587–1590Google Scholar
  26. 26.
    Forrest RA (2007) The European transmutation file: EAF-2007 decay data library. EURATOM/UKAEA Fusion AssociationGoogle Scholar

Copyright information

© Springer Nature Singapore Pte Ltd. 2019

Authors and Affiliations

  • Yican Wu
    • 1
  1. 1.Institute of Nuclear Energy Safety Technology (INEST)Chinese Academy of SciencesHefeiChina

Personalised recommendations