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JAEA Reports

Document collection of the 37th Technical Special Committee on Fugen Decommissioning

Nakamura, Yasuyuki; Koda, Yuya; Yamamoto, Kosuke; Soejima, Goro; Iguchi, Yukihiro

JAEA-Review 2020-002, 40 Pages, 2020/05

JAEA-Review-2020-002.pdf:8.78MB

Fugen Decommissioning Engineering Center, in planning and carrying out our decommissioning technical development, has been establishing "Technical special committee on Fugen decommissioning" which consists of the members well-informed, aiming to make good use of Fugen as a place for technological development which is opened inside and outside the country, as the central point in the energy research and development base making project of Fukui prefecture, and to utilize the outcome in our decommissioning to the technical development effectively. This report compiles presentation materials "The Current Situation of Fugen Decommissioning", "Development of Dismantling Mon-hours Estimated system by Achieved Data in Fugen", "Future Plan Based on the Operational Status of Clearance System" and "The Result and Future Plan of the Sampling work from Core Internal of Fugen", presented in the 37th Technical special committee on Fugen decommissioning which was held on December 2, 2019.

Journal Articles

Sampling and treatment of rock cores and groundwater under reducing environments of deep underground

Ebashi, Katsuhiro; Yamaguchi, Tetsuji; Tanaka, Tadao; Araki, Kunio*; Saito, Masao*

JAERI-Conf 2005-007, p.242 - 247, 2005/08

no abstracts in English

JAEA Reports

Improvement of the technique for stack monitoring based on behavior analysis of natural radio-nuclides; The technique for reducing the value of the exhaust monitor's background

Izaki, Kenji; Noda, Kimio; ; Kashimuta, Yoshio*

JNC-TN8410 2001-005, 30 Pages, 2001/01

JNC-TN8410-2001-005.pdf:0.62MB

Stack monitoring is the most important work in radiation control works. Exhaust monitors used for stack monitoring have the background (which is the counts by natural radio-nuclides) on normal condition, and the values of the background vary with the facilities. Therefore, if the value of background is high, it is difficult to estimate rapidly the radioactive concentration in the exhaust. In order to estimate rapidly the radioactive concentration in exhaust, we analyzed the behavior of natural radioactivity in the facilities and examine the technique fo reducing the value of the background. As a result of the examination, we found that it is possible to estimate rapidly if we change over the monitoring point to immediately after the HEPA filters on the exhaust duct. In this reports, the analyzed results of behavior of natural radio-nuclides in the facilities and the technique for reducing the values of the background are described. To reduce the value of the background has a major effect on not only rapidly estimating the radioactive density in the exhaust but also finding the unusual things on stack monitoring.

JAEA Reports

JOYO coolant sodium and cover gas purity control database (MK-II core)

; ; Saikawa, Takuya*; Sukegawa, Kazuya*

JNC-TN9410 2000-008, 66 Pages, 2000/03

JNC-TN9410-2000-008.pdf:1.39MB

The experimental fast reactor "JOYO" served as the MK-II irradiation bed core for testing fuel and material for FBR development for 15 years from 1982 to 1997. During the MK-II operation, impurities concentrations in the sodium and the argon gas were determined by 67 samples of primary sodium, 81 samples of secondary sodium, 75 samples of primary argon gas, 89 samples of secondary argon gas (the overflow tank) and 89 samples of secondary argon gas (the dump tank). The sodium and the argon gas purity control data were accumulated from in thirty-one duty operations, thirteen special test operations and eight annual inspections. These purity control results and related plant data were compiled into database, which were recorded on CD-ROM for user convenience. Purity control data include concentration of oxygen, carbon, hydrogen, nitrogen, chlorine, iron, nickel and chromium in sodium, concentration of oxygen, hydrogen, nitrogen, carbon monoxide, carbon dioxide, methane and helium in argon gas with the reactor condition.

Journal Articles

Evaluation on the radioactive inventories for the research reactor decommissioning

Arigane, Kenji

Dai-14-Kai Rikkyo Daigaku Gensiryoku Kenkyujo Koenkai Rombunshu (IAERU-9904), p.19 - 29, 2000/00

no abstracts in English

JAEA Reports

QA issues for site hydrochemical data used for groundwater evolution models

Sasamoto, Hiroshi; Yui, Mikazu; D.Savag*; Bille, B.*

JNC-TN8400 99-025, 32 Pages, 1999/06

JNC-TN8400-99-025.pdf:1.94MB

Groundwater data used for modelling site or repository evolution need to be assessed for their quality and whether they are "fit for purpose", prior to utilization. This report discuss factors and issues which impinge upon the quality of such data. It is recommended that geochemical modelleres : (1)are aware of how groundwater samples were collected, whether during drilling, during hydraulic testing, or thereafter, by in-situ measurement, pumped from boreholes, or by pressurised sampler ; (2)are aware of what procedures (if any) were used to "correct" samples for drill fluid contamination and what errors were associated with those methods ; (3)are aware of whether samples were subject to de-pressurisation during sampling, and whether geochemical modelling techniques were applied to correct the compositions of samples for that process ; (4)request different measures of redox activity (e.g., electrode measurements of Eh, concentrations of different redox-sensitive aqueous species) to be applied to key groundwater samples to investigate the extent of redox equilibrium ; (5)are aware of how groundwater samples were filtered and preserved for off-site analysis ; (6)ensure that adequate methods of groundwater filtration ($$<$$ 0.1$$mu$$m) and chemical analysis are applied to ensure accurate and reproducible analyses for dissolved aluminum at low levels of concentration (generally less than 0.2 mg/L) ; (7)are aware of elemental errors and detection limits in chemical analysis of groundwater samples and assess the quality of groundwater analyses via ion exchange balances and via a comparison of measured and calculated values for total dissolved solids contents. (8)ensure that detailed mineralogical analysis is carried out on rock samples from locations where key groundwater samples have been extracted.

JAEA Reports

None

Hirata, Yoichi*; *

PNC-TJ7439 98-003, 171 Pages, 1998/08

PNC-TJ7439-98-003.pdf:15.85MB

None

JAEA Reports

Report for marine environmental surveillance

; ; Isozaki, Tokuju; ; ; *

PNC-TN8440 97-037, 501 Pages, 1997/10

PNC-TN8440-97-037.pdf:9.02MB

None

JAEA Reports

None

*; Inoue, Motoi*

PNC-TJ7704 97-001, 45 Pages, 1997/01

PNC-TJ7704-97-001.pdf:8.78MB

no abstracts in English

JAEA Reports

None

; ; ; ; Isozaki, Tokuju;

PNC-TN8440 95-032, 458 Pages, 1995/09

PNC-TN8440-95-032.pdf:15.93MB

None

JAEA Reports

None

; ; ; Isozaki, Tokuju;

PNC-TN8520 94-003, 303 Pages, 1994/01

PNC-TN8520-94-003.pdf:12.68MB

None

JAEA Reports

None

Hirata, Yoichi*

PNC-TJ7439 94-001, 90 Pages, 1994/01

PNC-TJ7439-94-001.pdf:5.95MB

no abstracts in English

JAEA Reports

Preliminary investigation on determination of radionuclide distribution in field tracing test site

Tanaka, Tadao; Guo, Z.*; Mukai, Masayuki; Takebe, Shinichi; S.Li*; *

JAERI-M 93-235, 17 Pages, 1993/12

JAERI-M-93-235.pdf:0.55MB

no abstracts in English

JAEA Reports

None

Hosobori, Kenji*; Toyooka, Yoshinori*; Sakai, Yukio*

PNC-TJ1411 93-001, 945 Pages, 1993/01

None

JAEA Reports

None

; Seo, Toshihiro; ; ; Ogata, Nobuhisa; ; Yanagizawa, Koichi

PNC-TN7510 92-007, 27 Pages, 1992/07

PNC-TN7510-92-007.pdf:1.81MB

None

JAEA Reports

None

; Sumino, Kozo; ; ; ; ; Terunuma, Seiichi

PNC-TN9410 91-376, 79 Pages, 1991/11

PNC-TN9410-91-376.pdf:1.9MB

None

JAEA Reports

None

*; *; *; Sudo, Ken*

PNC-TJ7449 91-001VOL1, 406 Pages, 1991/05

PNC-TJ7449-91-001VOL1.pdf:3.51MB

no abstracts in English

JAEA Reports

Mechanical properties on high Cr-Mo steels at elevated temperature.(III); Creep properties of high Cr-Mo steel forgings (250$$sim$$280mmt)

; ; Yoshida, Eiichi;

PNC-TN9410 91-099, 106 Pages, 1991/02

PNC-TN9410-91-099.pdf:5.72MB

This stady was performed in order to confirm the influence of sampling method on Creep properties of 9Cr-Mo steel forgings which are promising as candidate materials for steam generator of large scale fast breeder reactor. This results are to be reflected on fundation of materials strength standard. Test materials are four kinds of 9Cr-Mo steel forgings (thickness:250$$sim$$280mmt) such as Mod.9Cr-1Mo (F4, F8 heats), 9Cr-1Mo-Nb-V(G3 heat), 9Cr-2Mo (H6 heat) steels. Results obtained are summarized as follows. (1)In order to evaluation of fundamental material properties, creep-rupture data on three kinds of 9Cr-Mo steel forgings such as Mod.9Cr-1Mo, 9Cr-2Mo and 9Cr-1Mo-Nb-V steels was obtained up to 10,000 hours. (2)The Mod.9Cr-1Mo steel exhibited most excellent creep-rupture strength and the 9Cr-2Mo steel was the worst among the three. (3)The effect of the sampling location of specimens on creep strength was not significant for Mod.9Cr-1Mo steel. But for 9Cr-1Mo-Nb-V steel and 9Cr-2Mo steel, longer creep rupture time was observed with spcimens taken from just below the center of the surface with direction of L, and shorter creep rupture time was observed for those taken from t/2 thickness at the center with direction of Z. (4)Creep strength of 9Cr-2Mo steel was lower than that of Mod.9Cr-1Mo (F4, F8)and 9Cr-1Mo-Nb-V steel. But rupture elongation and reduction of area of 9Cr-2Mo steel was greater than hat of other three materials, irrespective of the sampling location of specimens.

JAEA Reports

None

Obayashi Corporation*; Kajima Corporation*; *; *

PNC-TJ1449 91-006, 68 Pages, 1991/01

PNC-TJ1449-91-006.pdf:1.9MB

None

JAEA Reports

None

PNC-TN7410 89-009, 13 Pages, 1988/11

PNC-TN7410-89-009.pdf:0.17MB

None

23 (Records 1-20 displayed on this page)