Implementation of Transient Neutron Transport Solver in ASTERIA-FBR | Zendy

Toshihisa Yamamoto | Zendy; Hiroshi Endô | Zendy; Tsugio Yokoyama | Zendy; Masatoshi Kawashima | Zendy

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Implementation of Transient Neutron Transport Solver in ASTERIA-FBR

Author(s) -

Toshihisa Yamamoto,

Hiroshi Endô,

Tsugio Yokoyama,

Masatoshi Kawashima

Publication year - 2011

Publication title -

progress in nuclear science and technology

Language(s) - English

Resource type - Journals

ISSN - 2185-4823

DOI - 10.15669/pnst.2.253

Subject(s) - solver , neutron transport , transient (computer programming) , computer science , nuclear engineering , neutron , computational science , physics , nuclear physics , operating system , programming language , engineering

Numerical methods were newly developed to perform transient calculation based on the α -mode with a multigroup Monte Carlo code GMVP. Two methods to search α were investigated; one is a Newton-based-method with a use of adjoint solution, and the other is a quasi-Newton-method, which does not require the adjoint solution. The feasibility of the latter method was verified through numerical tests. The whole structure of the neutronic calculation module is shown together with some experience concerning with tally setting.

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