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Journal Articles

Dissolution behavior of slag in cement-equilibrated aqueous solutions

Maeda, Toshikatsu; Bamba, Tsunetaka*; Mizuno, Tsuyoshi*; Terakado, Shogo; Kitagawa, Isamu; Numata, Masami

Haikibutsu Gakkai Rombunshi, 17(4), p.271 - 281, 2006/07

no abstracts in English

Journal Articles

Dissolution behavior of slag in the presence of cement

Maeda, Toshikatsu; Bamba, Tsunetaka*; Hotta, Katsutoshi*; Mizuno, Tsuyoshi*; Ozawa, Tatsuya

Nippon Genshiryoku Gakkai Wabun Rombunshi, 4(4), p.242 - 247, 2005/12

no abstracts in English

Journal Articles

Development of Rock-like Oxide Fuel, an innovative nuclear fuel for burning plutonium

Yamashita, Toshiyuki

Seramikkusu, 39(10), p.817 - 821, 2004/10

no abstracts in English

Journal Articles

Characterization of 50L-scale solidified products yielded by melting treatment of miscellaneous solid wastes and evaluation of radioisotope tracer distribution

Nakashio, Nobuyuki; Nakashima, Mikio; Hirabayashi, Takakuni*

Nippon Genshiryoku Gakkai Wabun Rombunshi, 3(3), p.279 - 287, 2004/09

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

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

 Times Cited Count:8 Percentile:47.72(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

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.

JAEA Reports

None

*;

PNC-TN6510 94-001, 19 Pages, 1994/09

PNC-TN6510-94-001.pdf:0.65MB

no abstracts in English

JAEA Reports

None

; ; ; ;

PNC-TN8410 94-078, 57 Pages, 1994/07

PNC-TN8410-94-078.pdf:1.08MB

None

JAEA Reports

None

PNC-TN8600 92-011, 77 Pages, 1992/12

PNC-TN8600-92-011.pdf:3.72MB

no abstracts in English

JAEA Reports

Results of seventeen years leaching tests of simulated high level waste-phosphate glass

Kikuchi, Teruo; Iwamoto, Kazumi*

JAERI-M 92-146, 14 Pages, 1992/10

JAERI-M-92-146.pdf:0.77MB

no abstracts in English

JAEA Reports

None

Sonobe, Hitoshi; Ishiguro, Katsuhiko

PNC-TN8410 92-114, 85 Pages, 1992/03

PNC-TN8410-92-114.pdf:4.03MB

None

Journal Articles

Factor of dilution with freshly pumped leachant in continuous-flow leach tests on high-level waste glass

; ;

Journal of Nuclear Science and Technology, 26(8), p.811 - 813, 1989/08

no abstracts in English

Journal Articles

Continuous-flow leach tests of simulated high-level waste glass in synthesized groundwater and deionized water

; ;

Journal of Nuclear Science and Technology, 24(4), p.308 - 314, 1987/04

 Times Cited Count:5 Percentile:48.4(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Effects of crystalline phases on leaching of a devitrified simulated high-level waste glass

; ;

Waste Management, 6, p.223 - 231, 1986/00

no abstracts in English

JAEA Reports

Leaching Testes of the Readioative Glass Waste Form

; ; ;

JAERI-M 84-140, 12 Pages, 1984/08

JAERI-M-84-140.pdf:0.51MB

no abstracts in English

JAEA Reports

PIC-Container for Containment and Disposal of Low and Intermediate Level Radioactive Wastes

; *; ; *; *; *

JAERI-M 9389, 13 Pages, 1981/03

JAERI-M-9389.pdf:0.57MB

no abstracts in English

30 (Records 1-20 displayed on this page)