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本レポートは独立行政法人日本原子力研究開発機構が不定期に発行する成果報告書です 本レポートの入手並びに著作権利用に関するお問い合わせは 下記あてにお問い合わせ下さい なお 本レポートの全文は日本原子力研究開発機構ホームページ (http://www.jaea.go.jp) より発信されています 独立行政法人日本原子力研究開発機構研究技術情報部研究技術情報課 319-1195 茨城県那珂郡東海村白方白根 2 番地 4 電話 029-282-6387, Fax 029-282-5920, E-mail:ird-support@jaea.go.jp This report is issued irregularly by Japan Atomic Energy Agency Inquiries about availability and/or copyright of this report should be addressed to Intellectual Resources Section, Intellectual Resources Department, Japan Atomic Energy Agency 2-4 Shirakata Shirane, Tokai-mura, Naka-gun, Ibaraki-ken 319-1195 Japan Tel +81-29-282-6387, Fax +81-29-282-5920, E-mail:ird-support@jaea.go.jp Japan Atomic Energy Agency, 2008

1 1 1 2 2 2 2 (2008 2 29 ) 1 319-1194 4-33 1 2

Stabilization of Simulated Radioactive Lead Waste and Simulated Low Level Radioactive Liquid Waste Using Reformed Sulfur (Joint Research) Tomoyuki SONE, Toshiki SASAKI, Yasuaki MIYAMOTO, Hiromi YAMAGUCHI Haruka INOUE 1, Tsuyoshi KIHARA 1, Yoshihisa TAKEI 1, Takaiki TATEKAWA 2 Masaaki FUKAYA 2, Keishiro IRIYA 2 and Kunifumi TAKEUCHI 2 Waste Management Department Nuclear Fuel Cycle Engineering Laboratories Tokai Research and Development Center Japan Atomic Energy Agency Tokai-mura, Naka-gun, Ibaraki-ken (Received February 29, 2008) Cement solidification method has been developed for the stabilization of wastes containing lead contaminated with radioactive nuclides (Lead waste) and low level radioactive liquid waste (LLLW) generated during reprocessing of spent nuclear fuel at JAEA. However, for Lead waste the conversion of the lead to lead sulfide before solidifying with cement is essential to decrease the leachability of the lead. It is also required for LLLW to decrease the leachability of nitrate ion from the solidification product. It is considered that reformed sulfur solidification method (RSSM) has the possibility of solving these problems. Reformed sulfur (RS) that is produced by melting a mixture of sulfur and additives is superior in water interception, acid resistance and strength compared with cement. Therefore solidified Lead waste and solidified LLLW with RS should have the high resistance to leaching of the lead and the nitrate ion respectively. Unconfined compressive strength test and leaching test using solidified simulated Lead waste with RS and solidified simulated LLLW with RS were conducted to examine the applicability of RSSM as solidification technique of Lead waste and LLLW. Lead powder and lead oxide powder as simulated Lead waste and reagent mixture of which composition is equal to that of salts in LLLW as simulated LLLW were tested. The results of these studies show that RSSM is effective technique for stabilization of lead compared with cement solidification method because solidified lead with RS has much stronger resistance to leaching of lead than solidified lead with cement. It also show that the applicability of RSSM as solidification technique of the waste containing lead oxide and LLLW is low because the resistance to leaching of solidified lead oxide with RS and of solidified simulated LLLW with RS were equal to or lower than those of solidified products with cement respectively. Keywords : Reformed Sulfur, Lead, Low Level Liquid Waste, Stabilization, Leachability This work has been performed in JAEA as a joint research with Nippon Oil Corporation and Obayashi Corporation. 1 Nippon Oil Corporation 2 Obayashi Corporation

Contents 1. Introduction ----------------------------------------------------------------------------------------- 1 2. Stabilization with reformed sulfur ------------------------------------------------------------------- 2 2.1 Reformed sulfur solidified material ------------------------------------------------------ 2 2.2 Feature of reformed sulfur solidified material --------------------------------------------- 3 3. Experimental ------------------------------------------------------------------------------------- 3 3.1 Samples --------------------------------------------------------------------------------------- 3 3.1.1 Simulated waste -------------------------------------------------------------------------- 3 3.1.2 Stabilization material --------------------------------------------------------------------- 3 3.2 Treatment procedures ----------------------------------------------------------------------- 3 3.2.1 Solidification of simulated waste -------------------------------------------------- 4 3.2.2 Unconfined compressive strength test ------------------------------------------------ 4 3.2.3 Leaching test -------------------------------------------------------------------------------- 4 3.2.4 Uniformity of waste form --------------------------------------------------------------- 5 3.2.5 Test for hazardous material judgment ------------------------------------------------ 5 3.2.6 Applicability of reformed sulfur solidification method -------------------------- 5 4. Results and Discussion ----------------------------------------------------------------------- 6 4.1 Solidified lead and lead monoxide ----------------------------------------------------- 6 4.1.1 Unconfined compressive strength test --------------------------------------------- 6 4.1.2 Leaching test --------------------------------------------------------------------------- 6 4.1.3 Uniformity of waste form ------------------------------------------------------------ 7 4.1.4 Test for hazardous material judgment ---------------------------------------------- 7 4.2 Solidified simulated nitrate solution waste and slurry waste -------------------------- 7 4.2.1 Unconfined compressive strength test --------------------------------------------- 7 4.2.2 Leaching test -------------------------------------------------------------------------------- 8 4.2.3 Uniformity of waste form ------------------------------------------------------------ 8 4.2.4 Test for hazardous material judgment ------------------------------------------------ 8 5. Applicability of reformed sulfur solidification method ----------------------------------- 9 5.1 Radioactive lead waste ------------------------------------------------------------------------ 9 5.2 Low level radioactive liquid waste ------------------------------------------------------------ 9 6. Conclusion --------------------------------------------------------------------------------------------- 10 References -------------------------------------------------------------------------------------------- 11

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