Fast Neutron Dosimetry by <SUP>238</SUP>U(<I>n</I>, 2n) Reaction together with Thermal Neutron Dosimetry by <SUP>238</SUP>U(<I>n</I>, γ) Reaction

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概要

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• The fast neutron flux in the central thimble of a TRIGA-II reactor was estimated by using the <SUP>238</SUP>U(n, 2n)<SUP>237</SUP>U reaction as flux monitor. The thermal neutron flux also was estimated by <SUP>238</SUP>U(n, γ)→<SUP>239</SUP>Np and <SUP>232</SUP>Th(n, γ) →<SUP>233</SUP>Pa reactions. The latter flux was further measured at the same time by γ-ray spectrometry of the product nuclides and by chemical separation and β counting with α emitting isotopes as tracer. The values of flux thus obtained were compared with those estimated from the amounts of <SUP>28</SUP>Al, <SUP>27</SUP>Mg and <SUP>24</SUP>Na respectively produced by the (n, γ), (n, p) and (n, α) reactions on <SUP>27</SUP>Al. Furthermore, for the first time, the effective cross section for the <SUP>238</SUP>U(n, 2n)<SUP>237</SUP>U reaction was estimated to be 2.8b from a comparison with that for the <SUP>27</SUP>Al(n, α)<SUP>24</SUP>Na reaction.

• 一般社団法人 日本原子力学会の論文

著者

• SAKANOUE Masanobu

  Radiochemical Laboratory, Department of Chemistry, Faculty of Science, Kanazawa University

• MATSUURA Masataka

  Radiochemical Laboratory, Department of Chemistry, Faculty of Science, Kanazawa University

• SAEKI Masakatsu

  Radiochemical Laboratory, Department of Chemistry, Faculty of Science, Kanazawa University

関連論文

• Fast Neutron Dosimetry by 238U(n, 2n) Reaction together with Thermal Neutron Dosimetry by 238U(n, γ) Reaction

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