中ちゅう性せい子し束そく

noun

neutron flux

Technical term in nuclear physics and reactor engineering; refers to the number of neutrons passing through a unit area per unit time.

• 原げん子し炉ろ内ないの中ちゅう性せい子し束そくを測そく定ていする。

  Measure the neutron flux inside the nuclear reactor.