2021 Annual Meeting

Presentation information

Oral presentation

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

[1B07-11] Uncertainty Evaluation

Wed. Mar 17, 2021 2:45 PM - 4:15 PM Room B (Zoom room 2)

Chair: Kenichi Tada (JAEA)

3:45 PM - 4:00 PM

[1B11] Nuclear Data-induced Uncertainty Quantification of Prompt Neutron Decay Constant for Water-only System

*Tomohiro Endo1, Akihiro Noguchi1, Akio Yamamoto1 (1. Nagoya Univ.)

Keywords:prompt neutron decay constant, first-order perturbation theory, sensitivity analysis, uncertainty quantification, light water

To quantify the nuclear data-induced uncertainty of prompt neutron decay constant α for a non-neutron multiplication system, we developed an inhouse calculation code using SN method and power iteration. Based on the first-order perturbation theory, sensitivity analysis and uncertainty quantification of α with respect to nuclear data were carried out for pulsed neutron source experiments, which were conducted for water tank systems in the following study: https://doi.org/10.1080/18811248.1966.9732325