JOPSS - Search Results

Large-scale melting tests of simulated miscellaneous solid wastes were conducted to characterize solidified products (50L-drum size). Two heating modes were adopted in the tests: hybrid heating and induction heating modes. In the former, wastes were heated with both an induction furnace and a plasma torch, and in the latter, an electrically-conductive crucible was used with the induction furnace. Visual observation, chemical analysis and radioactivity measurements were conducted to the solidified products. It was found that the radioisotope distribution of solidified products was almost homogeneous. There was no remarkable deterioration in the solidified products subsequent to the leaching test.

Journal Articles

Effects of basicity and leachant pH on the dissolution rates of molten slag

Maeda, Toshikatsu; Bamba, Tsunetaka*; Mizuno, Tsuyoshi*

Haikibutsu Gakkai Rombunshi, 15(1), p.45 - 51, 2004/01

https://doi.org/10.3985/jswme.15.45

no abstracts in English

Journal Articles

Durability test of irradiated rock-like oxide fuels

Kuramoto, Kenichi; Shirasu, Noriko; Yamashita, Toshiyuki

Journal of Nuclear Materials, 319(1-3), p.180 - 187, 2003/06

https://doi.org/10.1016/S0022-3115(03)00149-1

Times Cited Count：9 Percentile：53.35(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Annual report on operation, utilization and technical development of Hot Laboratories; From April 1, 2000 to March 31, 2001

Department of Hot Laboratories

JAERI-Review 2001-044, 95 Pages, 2001/12

JAERI-Review-2001-044.pdf:6.55MB

no abstracts in English

Journal Articles

Leaching tests of simulated COGEMA bituminized waste form

Nakayama, Shinichi; Akimoto, Toshiyuki; Iida, Yoshihisa; Nagano, Tetsushi

Proceedings of International Conference on Scientific Research on the Back-end of the Fuel Cycle for the 21st Century (ATALANTE 2000) (Internet), 4 Pages, 2000/00

no abstracts in English

Journal Articles

Use of emanation thermal analysis in charcterization of leached surface of perovskite ceramics containing simulated TRU elements

V.Balek*; Z.Malek*; Mitamura, Hisayoshi; Bamba, Tsunetaka

Proc. of 7th Int. Conf. on Radioactive Waste Management and Environmetnal Remediation (ICEM'99)(CD-ROM), 4 Pages, 1999/00

no abstracts in English

JAEA Reports

Nuclear waste glass alteration in silica saturated solution depth profiling by ERDA and ESCA for simulated nuclear waste/ glass

; Kubota, Mitsuru*; *; *

JNC TN8430 98-001, 12 Pages, 1998/11

JNC-TN8430-98-001.pdf:0.87MB

Leaching experiments were performed with simulated nuclear waste glasses in silica saturated water at 90 $^{circ}$ C for periods of 28 days in order to clarify the alteration mechanism of waste glass under silica saturation. After leaching experiments, the depth profiles of some elements of glass surfaces were measured by ERDA and ESCA. Depth profiles of H and soluble elements, such as B and Na, for the simulated nuclear waste glass after leaching experiments demonstrated the formation of glass hydration layer and the depletion of soluble elements in the glass hydration layer. The results suggest that alteration of nuclear waste glass under silica saturation is attributed to glass hydration and the leaching behaviour of soluble elements depends on the growth of the glass hydration layer.