Application of the generally available WIMS versions to modern PWRs

• Autorzy: Kulikowska T. , Stadnik A. , Andrzejewski K. , Boettcher A.
• Języki publikacji: EN

Abstrakty

EN

The generally available versions of WIMS (Winfrith improved multigroup scheme) code have been used at the Institute of Atomic Energy POLATOM (IEA POLATOM, Otwock/Świerk, Poland) for a variety of reactor lattice analyses since 1974. With planned construction of new generation PWRs (power water reactors) in Poland, a question of WIMSD-5B version applicability to lattice calculations of strongly heterogeneous assemblies with gadolinium poisoned pins became actual. The present paper deals with modeling of the fuel assemblies using the version of WIMSD-5B extended at the IEA POLATOM. It was shown that with a careful choice of computational options the code properly describes main physical parameters of modern PWR fuel assemblies.

Słowa kluczowe

EN

reactor calculations; lattice spectrum code; resonance integrals; gadolinium bearing fuel

• Wydawca: Institute of Nuclear Chemistry and Technology
• Czasopismo: Nukleonika
• Rocznik: 2012
• Tom: Vol. 57, No. 1
• Strony: 87--93
• Opis fizyczny: Bibliogr. 9 poz., rys.

Twórcy

autor

Kulikowska T.

autor

Stadnik A.

autor

Andrzejewski K.

autor

Boettcher A.

• Institute of Atomic Energy POLATOM, 05-400 Otwock/Świerk, Poland, Tel.: [phone], Fax: [phone],

Bibliografia

• 1. Askew JR, Fayers FJ, Kemshell FB (1966) A general description of the lattice code WIMS. J Br Nucl Energy Soc 5;4:564
• 2. Deen JR, Woodruff WL, Costescu CI, Leopando LS (2004) WIMS-ANL User Manual. Rev. 6, ANL/TD/TM-99-07
• 3. Leszczynski F, Lopez Aldama D, Trkov A (2007) WIMS-D library update. International Atomic Energy Agency,Vienna, http://www-nds.iaea.org/publication/tecdocs/sti-pub-1264.pdf
• 4. NEA-1507 WIMSD5 (2004) WIMSD5, Deterministic Multigroup Reactor Lattice Calculations, http://www.oecd-nea.org/tools/abstract/detail/NEA-1507
• 5. Newton TD, Hutton JL (2002) The next generation WIMS lattice code: WIMS9. In: Proc of the PHYSOR 2002, Int Conf on the New Frontiers of Nuclear Technology, 7–10 October 2002, Seoul, Korea. American Nuclear Society
• 6. Trkov A (1994) GNOMER – multigroup 3-dimensional neutron diffusion nodal code with thermohydraulic feedbacks. IJS-DP-6688, Rev. 2
• 7. Trkov A, Ravnik M (1994) CORD-2 Package for PWR Nuclear Core Design Calculations. In: Proc of the Int Conf on Reactor Physics and Reactor Computations, 23–26 January 1994, Tel-Aviv, Israel
• 8. US EPR Final Safety Analysis Report, http://adamswebsearch2. nrc.gov/idmws/ViewDocByAccession.asp? AccessionNumber=ML092450764
• 9.X-5 Monte Carlo Team (2008) MCNP – A General Monte Carlo N-Particle Transport Code. Version 5. LA-CP-03-0284