Evaluation of delayed neutron data for thermal fission of U-235 based on integral experiments at semi-homogeneous experiment.

• KANEKO Yoshihiko

  Japan Atomic Energy Research Institute

• AKINO Fujiyoshi

  Japan Atomic Energy Research Institute

• YAMANE Tsuyoshi

  Japan Atomic Energy Research Institute

抄録

Evaluation of the delayed neutron data for thermal fission of ²³⁵U is attempted through an indirect method based on the comparison between measured and calculated integral quantities such as kinetic parameters and reactivity worths of fuel rods and burnable poison rods for the critical assembly Semi-Homogeneous Experiment (SHE). The most probable values for both of the effective delayed neutron fraction β_eff f and the decay constants λ's of delayed neutron precursors are determined from the condition that the sum of the squared deviations of the ratios of calculated to measured values from unity is minimized for the integral quantities, The most probable value of β_eff obtained in the present work is significantly large compared with that obtained with the Keepin's delayed neutron data set, and is closer to the value obtained with the ENDF/B-V data file than that with the ENDF/B-IV. On the other hand, the most probable λ values obtained in the present work are not away from those for thermal fission filed in the Keepin's delayed neutron data set.

収録刊行物

• Ｊｏｕｒｎａｌ　ｏｆ　Ｎｕｃｌｅａｒ　Ｓｃｉｅｎｃｅ　ａｎｄ　Ｔｅｃｈｎｏｌｏｇｙ（日本原子力学会英文論文誌）

  Ｊｏｕｒｎａｌ　ｏｆ　Ｎｕｃｌｅａｒ　Ｓｃｉｅｎｃｅ　ａｎｄ　Ｔｅｃｈｎｏｌｏｇｙ（日本原子力学会英文論文誌） 25 (9), 673-681, 1988

  一般社団法人 日本原子力学会

キーワード

• delayed neutrons
• thermal fission
• uranium 235
• integral experiments
• kinetic parameter
• reactivity worth
• effective delayed neutron fraction
• decay constants
• energy spectra
• least squares method
• comparative evaluations

詳細情報

• CRID: 1390001204094960384
• NII論文ID: 130000826897
• DOI: 10.3327/jnst.25.673
• COI: 1:CAS:528:DyaL1cXlvFyksLg%3D
• ISSN: 18811248
• ISSN: 00223131
• 本文言語コード: en
• データソース種別:
  • JaLC
  • Crossref
  • CiNii Articles
• 抄録ライセンスフラグ: 使用不可