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JAEA Reports

Measurements of thermal properties of buffer materials; Measurement of physical properties of buffer materials and improvement of measuring method

*

JNC TJ8400 2000-017, 74 Pages, 2000/02

JNC-TJ8400-2000-017.pdf:1.71MB

The report concerns the improvement of the method measuring thermal conductivity of buffer materials using a thermistor probe and the measurement of thermal conductivity of compacted bentonites and mixtures of bentonite and silica sand using the proposed method measuring thermophysical properties. The method measuring thermal conductivity is improved in accuracy and the apparatus is improved so as to measure easily with more short time. The calculated values of the conventional correlations predicting thermal conductivity of bentonite and mixture were compared with the exising and present data of thermal conductivity of bentonites and mixtures. The correlation proposed by Sakashita and Kumada can predict the best fitted values with the data of the bentonites and Fricke and Bruggeman correlations are fitted with the data for the mixtures with practical accuracy.

Journal Articles

Japan's energy strategy and future roles of nuclear energy

Sato, Osamu

Genshiryoku eye, 45(7), p.27 - 31, 1999/07

no abstracts in English

JAEA Reports

Journal Articles

Nuclear material from dismantled weapons, out flow of brain and nuclear waste on the disintegration of Soviet Union

Nihon Genshiryoku Gakkai-Shi, 36(3), p.190 - 192, 1994/00

no abstracts in English

JAEA Reports

None

; ; ;

PNC TN8440 92-004, 151 Pages, 1992/01

PNC-TN8440-92-004.pdf:3.54MB

None

Journal Articles

Density enhancement of polyethylene solidified wastes; Thickening with sodium sulfate anhydride

*; ; ; *

Journal of Nuclear Science and Technology, 19(5), p.410 - 418, 1982/00

 Times Cited Count:2 Percentile:32.87(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

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

Araki, Kunio; *; ; *; *; *

JAERI-M 9389, 13 Pages, 1981/03

JAERI-M-9389.pdf:0.57MB

no abstracts in English

Journal Articles

Density increase of polyethylene solidified wastes for sea disposal, (1); -Increase by cupper slag-

; ;

Journal of Nuclear Science and Technology, 18(2), p.162 - 168, 1981/00

 Times Cited Count:2 Percentile:36.87(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

JAEA Reports

JAEA Reports

Safety Assessment of the Radioactive Waste-Cement Composite,2; Leaching of $$^{6}$$$$^{0}$$Co from Solidified Cement Blocks

; ; ; ; Wadachi, Yoshiki;

JAERI-M 6361, 18 Pages, 1976/01

JAERI-M-6361.pdf:0.76MB

no abstracts in English

Journal Articles

NEA sea disposal operations and guideline of packing for radioactive wastes

Hoken Butsuri, 9(2), p.33 - 37, 1974/02

no abstracts in English

Journal Articles

Examination of the drum can dumping treatment method for radioactive waste fluid on the safety and the economy

*; Ishihara, Takehiko

Dai-3-Kai Genshiryoku Shimpojiumu Hobunshu, 2, P. 70, 1959/00

no abstracts in English

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