2019 Annual Meeting

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Oral presentation

III. Fission Energy Engineering » 301-1 Reactor Physics, Utilization of Nuclear Data, Criticality Safety

[3J09-11] Analysis Method Development (Monte-Carlo)

Fri. Mar 22, 2019 2:45 PM - 3:35 PM Room J (Common Education Bildg. 2 3F No.32)

Chair:Tomohiro Endo(Nagoya Univ.)

3:15 PM - 3:30 PM

[3J11] Time dependent neutron multiplication from point source in delayed super-critical core

*Yasushi Nauchi1 (1. CRIEPI)

Keywords:natural mode equation, reactor period, Monte Carlo method, elapsed time, power iteration

In a delayed super-critical core, a power iteration calculation from a point source is performed. During the iteration, time spectrum of neutron flux in reference to the source is tallied every cycle. By summation of the spectra weighted by the total product of ki, the time dependent neutron multiplication is evaluated.