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Depletion analysis of the HELIOS experiment using the MCB code

Treść / Zawartość
Identyfikatory
Warianty tytułu
Konferencja
Proceedings of the International Conference on Development and Applications of Nuclear Technologies NUTECH-2011, 11-14 September 2011, Kraków, Poland
Języki publikacji
EN
Abstrakty
EN
The focus of our studies is to present an advanced depletion analysis of the HELIOS experiment by means of the Monte Carlo continuous energy burn-up code (MCB). The MCB was used mainly to calculate nuclide density evolution in nuclear reactor cores. We present the capability of the MCB to investigate the depletion of nuclear fuel samples irradiated in the HELIOS experiment. In our studies we traced the behaviour of the main fissile isotopes, 242mAm and 239Pu, respectively. We also perform a sensitivity analysis to the choice of JEF2.2 and JEFF3.1 cross section libraries in terms of the released fission power and the evolution of actinide inventories. The amount of He produced at the end of irradiation, as well as Am and Pu depletion, were also considered.
Czasopismo
Rocznik
Strony
435--441
Opis fizyczny
Bibliogr. 18 poz., rys.
Twórcy
autor
autor
autor
autor
  • AGH University of Science and Technology, al. A. Mickiewicza 30, 30-059 Krakow, Poland and European Commission, Joint Research Centre, Institute for Energy, P. O. Box 2, 1755 ZG Petten, The Netherlands, Tel.: +48 12 617 4420, Fax: +48 12 634 0010, moettin@agh.edu.pl
Bibliografia
  • 1. Blachot J, Assal W, Blaise P et al. (2000) The JEF2.2 Nuclear Data Library. JEFF Report no. 17. NEA OECD
  • 2. Booth TE, Brown FB, Bull JS et al. (2005) X-5 Monte Carlo Team: MCNP-A General Monte Carlo N-Particle Transport Code. Version 5. LANL Report LA-UR-03-1987
  • 3. Cetnar J (2006) General solution of Bateman equations for nuclear transmutations. Ann Nucl Energ 33:640–645
  • 4. Cetnar J, Gudowski W, Wallenius J (1999) MCB: A continuous energy Monte Carlo burn-up simulation code. In: Proc of Actinide and Fission Product Partitioning and Transmutation. EUR 18898 EN, OECD/NEA 523
  • 5. Croff AG (1980) A User’s manual for the ORIGEN2 computer code. ORNL/TM-7157
  • 6. D’Agata E (2009) HELIOS, Irradiation of U-free fuels and targets for Am transmutation in a QUATRO rig with two sample holders at the HFR Petten. Project no. 325 002. Design and Safety Report, PUBSY no. JRC46049
  • 7. Döderlein C (2010) User guide for the improved neutronics schema for the interpretation of irradiation experiments in the HFR. Part 1: Calculation of the environment. European Commission, Directorate-General Joint Research Centre, Institute for Energy – Safety of Future Nuclear Reactors Unit, PUBSY no. JRC59903
  • 8. Firestone RB, Shirley VS (1996) Table of isotopes 8E. Wiley
  • 9. Forrest RA (2003) FISPACT-2003 User manual. EASY Documentation Series, UKAEA FUS 485
  • 10. Herman M, Trkov A (2009) ENDF-6 Formats Manual, Data Formats and Procedures for the Evaluated Nuclear Data File ENDF/B-VI and ENDF/B-VII, CSEWG Document ENDF-102. Report BNL-90365-2009
  • 11. Klaassen FC (2009) Project presentation, project’s full name FAIRFUELS. Contract (grant agreement) no. 232624, www.fp7-fairfuels.eu
  • 12. Klaassen FC, Schram RPC, Bakker K et al. (2002) Spinel inert matrix fuel testing at the HFR Petten. In: Proc of the 7th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, Jeju, Republic of Korea
  • 13. Koning A, Forrest R, Kellet M et al. (2006) The JEFF-3.1 Nuclear Data Library. JEFF Report no. 21. NEA OECD
  • 14. Konings RJM, Conrad R, Dassel G et al. (2000) The EFTTRA-T4 experiment on americium transmutation. Jur Nucl Mat 282:159–170
  • 15. Konings RJM, Mühling G, Conrad R et al. (1998) Transmutation of americium and technetium: Recent results of EFTTRA. In: Proc of 5th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation. SCK-CEN, Mol, Belgium
  • 16. Mann FM, Schenter RE (1977) Calculated neutron capture cross-section to the americium ground and isomer states. Nucl Sci Eng 63:242–249
  • 17. Shibata K, Iwamoto O, Nakagawa T et al. (2011) JENDL-4.0: A new library for nuclear science and engineering. J Nucl Sci Technol 48;1:1–30
  • 18.Wahl A (1985) Nuclear-charge distribution near symmetry for thermal-neutron-induced fission of 235U. Phys Rev C 32:184–194
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-article-BUJ8-0023-0029
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