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JAEA Reports

The Study on degradation of engineered barrier in radioactive waste repositories effect of nitrate and leaching solutions

Iriya, Keishiro*; *; Fujita, Hideki*; Kubo, Hiroshi*

JNC TJ8400 2000-034, 212 Pages, 2000/02

JNC-TJ8400-2000-034.pdf:7.91MB

Cementious materials and highly compacted bentnite are expectable candidates as materials of TRU waste repositories. It was pointed out that Bentonite might be changed to Zeolite and surrounding rock might be altered by high alkalinity water flow, since cement hydrate leached to pore water of cement and it was changed to alkaline. Transportation of radio-nuclides might be accelerated by organic materials, such as super plasticizer, and nitlate which is contained in nuclear wastes. It was concluded by previous studies that rock and bentonite is stable in alkaline water which pH is less than 10.5. The new type of low alkalinity cement with high silica fume and fly ash content which could keep pH below 11.0 was developed and its performance has been assessed. However since Zeolitation and ilitation were reported upon deterioration of bentonite bated in certain condition, it should be assessed by long term experiment. Since Capacity of keeping integrity of bentonite hasn't been directly checked by experiments upon the developed new type of low alkalinity cement it should be done. Although amount of leaching organic was quantitatively and experimentally assessed at an early age, effect of changing of amount and shape hasn't assessed in leaching of radio nuclides. Although it is pointed out that deterioration of cementitious materials isn't accelerated by condensed nitrate solution at early period after closure, it is considered that it might be accelerated corresponding to chemical composition in case of decrement of concentration of nitrate. In this study, deterioration of materials will be assessed in detail in order to feed back the results to assessment of transportation of radio nuclides. Long term deterioration of bentonite by leaching water of cement will be experimentally assessed, and deteriorating test of bentonite will be carried out by leaching water of low alkalinity cement. Amount of organic and component of it will be measured. Furthermore ...

JAEA Reports

The Study on degradation of engineered barrier in ratioactive waste repositories effect of nitrate and leaching solutions

Iriya, Keishiro*; *; Kubo, Hiroshi*; Fujita, Hideki*

JNC TJ8400 2000-033, 95 Pages, 2000/02

JNC-TJ8400-2000-033.pdf:11.11MB

Cementious materials and highly compacted bentnite are expectable candidates as materials of TRU waste repositories. It was pointed out that Bentonite might be changed to Zeolite and surrounding rock might be altered by high alkalinity water flow, since cement hydrate leached to pore water of cement and it was changed to alkaline. Transportation of radio-nuclides might be accelerated by organic materials, such as super plasticizer, and nitrate which is contained in nuclear wastes. It was concluded by previous studies that rock and bentonite is stable in alkaline water which pH is less than 10.5. The new type of low alkalinity cement with high silica fume and fly ash content which could keep pH below 11.0 was developed and its performance has been assessed. However since Zeolitation and ilitation were reported upon deterioration of bentonite bated in certain condition, it should be assessed by long term experiment. Since Capacity of keeping integrity of bentonite hasn't been directly checked by experiments upon the developed new type of low alkalinity cement it should be done. Although amount of leaching organic was quantitatively and experimentally assessed at an early age, effect of changing of amount and shape hasn't assessed in leaching of radio nuclides. Although it is pointed out that deterioration of cementitious materials isn't accelerated by condensed nitrate solution at early period after closure, it is considered that it might be accelerated corresponding to chemical composition in case of decrement of concentration of nitrate. In this study, deterioration of materials will be assessed in detail in order to feed back the results to assessment of transportation of radio nuclides. Long term deterioration of bentonite by leaching water of cement will be experimentally assessed, and deteriorating test of bentonite will be carried out by leaching water of low alkalinity cement. Amount of organic and component of it will be measured. Furthermore ...

JAEA Reports

Installation of Subsurface Hydrological Monitoring System in Regional Hydrogeological Study

Toyama, Shigeyuki*; Wakamatsu, Hisanori; Okazaki, Hikoya

JNC TJ7440 99-031, 22 Pages, 1999/09

JNC-TJ7440-99-031.pdf:6.36MB

no abstracts in English

JAEA Reports

None

*; *

JNC TJ1400 99-030, 102 Pages, 1999/03

JNC-TJ1400-99-030.pdf:4.0MB

no abstracts in English

JAEA Reports

Irradiation assisted stress corrosion cracking of austenitic stainless steels

Tsukada, Takashi

JAERI-Research 98-007, 187 Pages, 1998/03

JAERI-Research-98-007.pdf:17.46MB

no abstracts in English

Journal Articles

R&D-RC structure using electrical insulated reinforcing bar, part 13; Primary test of electrical concrete crack monitoring method

Akutsu, Yoichi; Okawa, Yoshinao; Suzuki, Hideyuki; *; *; *

Nihon Kenchiku Gakkai Taikai Gakujutsu Koen Kogaishu, 0, p.1337 - 1338, 1995/00

no abstracts in English

JAEA Reports

Study of through-thickness attenuation of irradiation embrittlement using JPDR pressure vessel

Suzuki, Masahide;

JAERI-Research 94-038, 23 Pages, 1994/11

JAERI-Research-94-038.pdf:0.87MB

no abstracts in English

JAEA Reports

None

;

PNC TN8420 94-026, 67 Pages, 1994/08

PNC-TN8420-94-026.pdf:2.47MB

None

Journal Articles

Neutron activation analysis of deposition samples in Tokai-mura, Japan and evaluation of resuspension of $$^{137}$$Cs

Ueno, Takashi; Amano, Hikaru; Kobayashi, Yoshii

Hoken Butsuri, 29(1), p.17 - 22, 1994/03

no abstracts in English

Journal Articles

Life extension of nuclear power plant, VI; Risk assessment of nuclear power plant with consideration of ageing

Muramatsu, Ken

Nihon Genshiryoku Gakkai-Shi, 36(5), p.387 - 390, 1994/00

no abstracts in English

JAEA Reports

Sectional observation of marine water in Tokai coastal area

; ; ; Isozaki, Tokuju;

PNC TN8450 93-004, 144 Pages, 1993/06

PNC-TN8450-93-004.pdf:2.0MB

Generally speaking, two kinds of water plumes which have different temperature, salinity and so on are not easily mixturred and have special boundary. So, it is possible to predict ocurrence of special boundary of sea water from observation of temperature, salinity of sea water. Not only marine environmental monitoring such as radioactivity analysis of sea water, sea-bed sediment, marine products but also observation of water current, water direction, surface and ventical observation of water temperature, salinity and so on in Tokai coastal area are carried out with some observation instruments by Environmental Protection Section, Tokai Works, PNC. The results of vertical observation from 1990 to 1991 are recorded in this report.

JAEA Reports

None

Kawamura, Kazuo*; Nakajima, Tatsuya*; Tomori, Masahiko*

PNC TJ7361 93-004, 91 Pages, 1993/03

PNC-TJ7361-93-004.pdf:8.99MB

no abstracts in English

Journal Articles

Research reactors in Japan; Present status in the world

Shirai, Eiji; Soyama, Kazuhiko

Genshiryoku Kogyo, 39(11), p.48 - 53, 1993/00

no abstracts in English

JAEA Reports

Sealing performance test for main flange of pressure vessel of T$$_{2}$$ test section in HENDEL

Ioka, Ikuo; *; Inagaki, Yoshiyuki; *; ; Suzuki, Kunihiro;

JAERI-M 90-221, 21 Pages, 1990/12

JAERI-M-90-221.pdf:0.68MB

no abstracts in English

JAEA Reports

The Effects of water environments on crack growth behavior of LWR pressure vessel steels

Onizawa, Kunio; ; ;

JAERI-M 90-202, 33 Pages, 1990/11

JAERI-M-90-202.pdf:1.15MB

no abstracts in English

Oral presentation

Study to evaluate leaching mass of elements from damaged fuels, 1; Leaching behavior of multiphase molten debris in the system of stainless steel and zircaloy

Ikeuchi, Hirotomo; Yano, Kimihiko; Watanabe, Masayuki; Koizumi, Kenji

no journal, , 

no abstracts in English

Oral presentation

Study on physical mechanism in aging phenomenon of fuel debris, 1; Transition of total crack length by cyclic temperature fluctuation

Suzuki, Seiya; Yano, Kimihiko; Watanabe, Masayuki; Koizumi, Kenji

no journal, , 

no abstracts in English

Oral presentation

Predict form change of fuel debris; Study on physical mechanism in aging phenomenon of fuel debris

Suzuki, Seiya; Yano, Kimihiko; Watanabe, Masayuki; Koizumi, Kenji

no journal, , 

no abstracts in English

Oral presentation

Study on physical mechanism in aging phenomenon of fuel debris, 2; Evaluation of fracture behavior in fuel debris by cyclic temperature fluctuation

Suzuki, Seiya; Yano, Kimihiko; Okamura, Nobuo; Watanabe, Masayuki

no journal, , 

no abstracts in English

Oral presentation

Study on physical mechanism in aging phenomenon of fuel debris, 3; Transition of total crack length by cyclic temperature fluctuation under water in solidified molten materials

Suzuki, Seiya; Arai, Yoichi; Okamura, Nobuo; Watanabe, Masayuki

no journal, , 

Clarification of aging phenomenon of fuel debris is one of the important issues because to evaluate that the safety during long term at defueling and storing. As a physical mechanism, we were investigated the effect of environmental temperature on the amount of cracks increased, and clarified the behavior of crack generation and propagation in submerged fuel debris.

24 (Records 1-20 displayed on this page)