Published May 2013 | Version v1
Journal article

Power spectral analysis for a thermal subcritical reactor system driven by a pulsed 14 MeV neutron source

  • 1. Kinki Univ., lnterdisciplinary Graduate School of Science and Engineering, Higashi-Osaka, Osaka (Japan)
  • 2. Kyoto Univ., Research Reactor Institute, Nuclear Engineering Science Division, Kumatori, Osaka (Japan)

Description

A series of power spectral analyses for a thermal subcritical reactor system driven by a pulsed 14 MeV neutron source was carried out at Kyoto University Critical Assembly (KUCA), to determine the prompt-neutron decay constant of the accelerator-driven system (ADS). The cross-power spectral density between time-sequence signal data of two neutron detectors was composed of a familiar continuous reactor noise component and many delta-function-like peaks at the integral multiple of pulse repetition frequency. The prompt-neutron decay constant inferred from the reactor noise component of the cross-power spectral density was consistent with that obtained by a pulsed neutron experiment. However, the reactor noise component of the auto-power spectral density of each detector was hidden by a white chamber noise in the higher-frequency range and this feature resulted in a considerable underestimation of the decay constant. For several runs with a low pulse-repetition frequency, furthermore, we attempted to infer the decay constant from point data of the delta-function-like peaks. The analysis for a run under a slightly subcritical state resulted in the consistent decay constant; however, those for other runs under significantly subcritical states underestimated the decay constant. Considering the contribution of a spatially higher mode to the point data, the above underestimation was solved to obtain the consistent decay constant. While the Feynman-α formula for a pulsed neutron source is too complicated to be fitted directly to variance-to-mean ratio data, the present analysis on frequency domain is much simpler and the conventional formula based on the first-order reactor transfer function is available for fitting to power spectral density data. (author)

Availability note (English)

Available from http://dx.doi.org/10.1080/00223131.2013.785268

Additional details

Identifiers

Publishing Information

Journal Title
Journal of Nuclear Science and Technology (Tokyo)
Journal Volume
50
Journal Issue
5
Journal Page Range
p. 481-492
ISSN
0022-3131

Optional Information

Notes
37 refs., 7 figs, 4 tabs.