Measurement and Analysis of Fission Rate Distributions of 237Np and 238U in a Polyethylene System with a 65 MeV Neutron Source.

• IWASAKI Tomohiko

  Department of Quantum Science and Energy Engineering, Tohoku University

• SAKUYA Yoshimasa

  Department of Quantum Science and Energy Engineering, Tohoku University

• HIRAKAWA Naohiro

  Department of Quantum Science and Energy Engineering, Tohoku University

• NAKASHIMA Hiroshi

  Tokai Establishment, Japan Atomic Energy Research Institute

• SAKAMOTO Yukio

  Tokai Establishment, Japan Atomic Energy Research Institute

• TAKADA Hiroshi

  Tokai Establishment, Japan Atomic Energy Research Institute

• TANAKA Susumu

  Takasaki Establishment, Japan Atomic Energy Research Institute

書誌事項

タイトル別名

• Measurement and Analysis of Fission Rat

抄録

Fission rates of ²³⁷Np and ²³⁸U in a polyethylene (CH₂) system were measured with a 65MeV quasi monoenergetic neutron source. Relative fission rate distributions dependent on polyethylene thickness up to about 70cm were obtained for both nuclides with the experimental error within 7%. The present experiment was analyzed by the NMTC/JAERI code that has been employed for designing accelerator-driven transmutation systems. The fission rates of both ²³⁷Np and ²³⁸U calculated by the NMTC/JAERI did not agree with the experimental ones. The C/E values for both were about 2.0 at 71.8cm of polyethylene thickness when both experimental and calculated values were normalized to 1.0 at 0.0cm of polyethylene thickness. A sensitivity analysis of the NMTC/JAERI was performed by changing cross sections and angular distributions of hydrogen and carbon and by employing three options of the intra-nuclear cascade/evaporation calculation of the NMTC/JAERI. The disagreement of the NMTC/JAERI calculation with the experimental values was partially improved by increasing the nonelastic-scattering cross section of carbon and by broadening the elastic-scattering angular distribution of carbon.

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） 35 (3), 169-177, 1998

  一般社団法人 日本原子力学会

キーワード

• transmutation
• accelerator-driven reactor
• MeV range 10-100
• neutron sources
• neutrons
• fission rate
• neptunium 237
• uranium 238
• polyethylene
• hydrogen
• carbon
• experimental data
• errors
• NMTC/JAERI
• MORSE-CG

詳細情報

• CRID: 1390001204094118144
• NII論文ID: 10002079080
• NII書誌ID: AA00703720
• DOI: 10.3327/jnst.35.169
• COI: 1:CAS:528:DyaK1cXivFOkt78%3D
• ISSN: 18811248
• ISSN: 00223131
• NDL書誌ID: 4440341
• Web Site: https://ndlsearch.ndl.go.jp/books/R000000004-I4440341
• 本文言語コード: en
• データソース種別:
  • JaLC
  • NDL
  • Crossref
  • CiNii Articles
• 抄録ライセンスフラグ: 使用不可