Diffusion of Ni in Compacted Sodium Bentonite.

• SATO Haruo

  Waste Technology Development Division Tokai Works Power Reactor and Nuclear Fuel Development Corp.

• YUI Mikazu

  Waste Technology Development Division Tokai Works Power Reactor and Nuclear Fuel Development Corp.

書誌事項

タイトル別名

• Diffusion of Ni in Compacted Sodium Ben

抄録

Diffusion coefficients of key nuclides in bentonite are one of the important parameters required for performance assessment of geological disposal of high-level radioactive waste (HLW). Diffusion is generally classified into two states: non-steady state and steady state. Nonsteady state diffusion represents the diffusion coefficient in a transient state, which is called apparent diffusion coefficient (Da). In performance assessment, Da is accounted as an important parameter for evaluating nuclide retardation in bentonite. Nickel-59 is produced by activation of the corrosion products in a power reactor and is one of the important radionuclides for performance assessment because of its long half-life of 7.5×10⁴ yr. Christiansen and Torstenfelt have reported Da of Ni in bentonitew⁽¹⁾. However, Da for Ni in Kunigel V1^R bentonite (Kunimine Industries Co., Ltd.), which is produced in Japan, has not been measured yet. In underground, such 1, 000m deep, bentonite temperature is higher than that of ground surface because of temperature gradient⁽²⁾. This temperature increase may affect diffusion behaviors of nuclides in bentonite. For example, it has been reported that the apparent diffusion coefficients for Cs, Na, HTO and Sr in bentonite become larger with increasing temperature^(3)-(7). However, studies for temperature dependence on diffusion of nuclides in compacted bentonite are quite limited. <BR>In this study, the apparent diffusion coefficients for Ni in Kunigel V1 were measured as functions of density of the bentonite and temperature, then the activation energy for diffusion was calculated from the temperature dependence of the Da.

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） 34 (3), 334-336, 1997

  一般社団法人 日本原子力学会

キーワード

• apparent diffusion coefficient
• diffusion
• ionic diffusion coefficient in free water
• sodium bentonite
• nickel
• activation energy
• temperature dependence
• density dependence
• highlevel radioactive waste
• geological disposal
• concentration dependence

詳細情報

• CRID: 1390001204096026752
• NII論文ID: 10002076856
• NII書誌ID: AA00703720
• DOI: 10.3327/jnst.34.334
• COI: 1:CAS:528:DyaK2sXivFWktrs%3D
• ISSN: 18811248
• ISSN: 00223131
• NDL書誌ID: 4176288
• Web Site: https://ndlsearch.ndl.go.jp/books/R000000004-I4176288
• 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