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JAEA Reports

The Arrangement of the seismic design method of the underground facility

Tanai, Kenji; Horita, M.*; *; Goke, Mitsuo*

JNC-TN8410 2001-026, 116 Pages, 2002/03

JNC-TN8410-2001-026.pdf:9.19MB

Earthquake resistance for the underground structure is higher than the ground structure. Therefore, the case of examining the earthquake resistance of underground structure was little. However, it carries out the research on the aseismic designing method of underground structure, since the tunnel was struck by Hyogo-ken Nanbu Earthquake, and it has obtained a much knowledge. However, an object of the most study was behavior at earthquake of the comparatively shallow underground structure in the alluvial plain board, and it not carry out the examination on behavior at earthquake of underground structure in the deep rock mass. In the meantime, underground disposal facility of the high level radioactive waste constructs in the deep underground, and it carries out the operation in these tunnels. In addition, it has made almost the general process of including from the construction start to the backfilling to be about 60 years (Japan Nuclear Fuel Cycle Development Institute, 1999). During these periods, it is necessary to also consider the earthquake resistance as underground structure from the viewpoint of the safety of facilities. Then, it extracted future problem as one of the improvement of the basis information for the decision of the safety standard and guideline of the country on earthquake-resistant design of the underground disposal facility, while it carried out investigation and arrangement of earthquake-resistant design cases, guidelines and analysis method on existing underground structure, etc.. And, the research item for the earthquake resistance assessment of underground structure as case study of the underground research laboratory.

JAEA Reports

The 4th technological meeting of Tokai Reprocessing Plant

; Maki, Akira; ; ; ; ; Fukuda, Kazuhito

JNC-TN8410 2001-023, 188 Pages, 2001/11

JNC-TN8410-2001-023.pdf:30.98MB

"The 4th technological meeting of Tokai Reprocessing Plant (TRP)" was held in JNFL Rokkasyo site on octorber 11$$^{th}$$, 2001. The report contains the proceedings, transparancies and questionnaires of themeetin. This time, we reported about "Maintenance and repair results of Tokai Reprocessing Plant" based on technology and knowledge accumulated in Tokai Reprocessing Plant.

JAEA Reports

The 3rd technological meeting of Tokai reprocessing plant

Maki, Akira; ; Taguchi, Katsuya; ; Shimizu, Ryo; Shoji, Kenji;

JNC-TN8410 2001-012, 185 Pages, 2001/04

JNC-TN8410-2001-012.pdf:9.61MB

"The third technological meeting of Tokai Reprocessing plant (TRP)" was held in JNFL Rokkasyo site on March 14$$^{th}$$, 2001. The technical meetings have been held in the past two times. The first one was about the present status and future plan of the TRP and second one was about safety evaluation work on the TRP. At this time, the meeting focussed on the corrosion experrience, in-service inspection technology and future maintenance plan. The report contains the proceedings, transparancies and questionnaires of the meeting are contained.

JAEA Reports

None

*; *

JNC-TJ8420 2000-010, 171 Pages, 2000/03

JNC-TJ8420-2000-010.pdf:5.34MB

no abstracts in English

JAEA Reports

None

Ono, Takahiro*; Higuchi, Takanao*; Kazama, T.*; Hashimoto, T.*; Seito, Y.*; Hattori, Tomomi*; Kanamori, Miwa*

JNC-TJ1420 2000-005, 257 Pages, 2000/03

JNC-TJ1420-2000-005.pdf:9.53MB

None

JAEA Reports

None

*; Ito, Kenji*; *; Oyamada, Kiyoshi*

PNC-TJ1561 95-001, 107 Pages, 1995/02

PNC-TJ1561-95-001.pdf:3.08MB

None

JAEA Reports

ORION-II; A Computer code to estimate environmental concentraion and dose due to airborne release of radioactive material

Shinohara, Kunihiko*; Asano, Tomohiro; Narita, Osamu

PNC-TN8410 87-17, 40 Pages, 1987/05

PNC-TN8410-87-17.pdf:2.05MB

A computer code ORION-II has been developed to estimate environmental concentraion and dose due to airborne release of radioactive material from multiple sources of nuclear fuel cycle facilities. The modified Gaussian plume model is applied to calculate atmospheric dispersion. The plume depletion models such as gravitational settling, dry deposition, precipitation scavenging and radioactive decay are considered as the causes of the depletion and deposition on the ground and vegetation. Dose to the public is calculated as an individual dose. Inhalation and oral intake are considered as internal pathways. Submersion in the radioactive cloud and external exposure to ground surface contamination are considered as external pathways. ORION-II is the updated version of ORION code (PNCT N841-83-42) and is appricable to the case study of environmental assessment for the nuclear fuel cycle facilities. ORION-II is written in FORTRAN-IV language and can be run on IBM 360, 370, 303X, 308X, 43XX, and FACOM M-series computers.

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