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Journal Articles

Experiment on density stratification behavior by containment venting using CIGMA Facility

Ishigaki, Masahiro; Abe, Satoshi; Shibamoto, Yasuteru; Yonomoto, Taisuke

Proceedings of 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18) (USB Flash Drive), p.5927 - 5940, 2019/08

no abstracts in English

Journal Articles

A Method for the prediction of the dose rate distribution in a primary containment vessel of the Fukushima Daiichi Nuclear Power Station

Okumura, Keisuke; Riyana, E. S.; Sato, Wakaei*; Maeda, Hirobumi*; Katakura, Junichi*; Kamada, So*; Joyce, M. J.*; Lennox, B.*

Progress in Nuclear Science and Technology (Internet), 6, p.108 - 112, 2019/01

In order to establish the prediction method of the dose rate distribution in the primary containment vessel (PCV) of the Fukushima Daiichi Nuclear Power Station, a series of calculations were carried out in the following way; (1) burnup calculation to obtain fuel composition at the time of accident, (2) activation calculation for the structural materials including impurities, (3) estimation of Cs contamination in PCV based on the result of severe accident analysis by IRID, (4) decay calculation of radioactive nuclides, (5) photon transport calculation to obtain dose rate distribution. After that, Cs concentration around the dry-well of 1F was modified to be consistent with locally measured dose rates in the PCV-investigation by IRID.

JAEA Reports

Verification of alternative dew point hygrometer for CV-LRT in Monju

Ichikawa, Shoichi; Chiba, Yusuke; Ono, Fumiyasu; Hatori, Masakazu; Kobayashi, Takanori; Uekura, Ryoichi; Hashiri, Nobuo*; Inuzuka, Taisuke*; Kitano, Hiroshi*; Abe, Hisashi*

JAEA-Research 2016-021, 32 Pages, 2017/02

JAEA-Research-2016-021.pdf:5.0MB

In order to reduce the influence on a plant schedule of the MONJU by the maintenance of dew point hygrometers, The JAEA examined a capacitance type dew point hygrometer as an alternative dew point hygrometer for a lithium-chloride type dew point hygrometer which had been used at the CV-LRT in the MONJU. As a result of comparing a capacitance type dew point hygrometer with a lithium-chloride type dew point hygrometer at the CV-LRT (Atmosphere: nitrogen, Testing time: 24 hours), there weren't significant difference between a capacitance type dew point hygrometer and a lithium-chloride type dew point hygrometer. As a result of comparing a capacitance dew point hygrometer with a high-mirror-surface type dew point hygrometer for long term verification (Atmosphere: air, Testing time: 24 months), the JAEA confirmed that a capacitance type dew point hygrometer satisfied the instrument specification ($$pm$$2.04$$^{circ}$$C) required by the JEAC4203-2008.

Journal Articles

Development of fast reactor containment safety analysis code, CONTAIN-LMR, 1; Outline of development project

Miyahara, Shinya; Seino, Hiroshi; Ohno, Shuji; Konishi, Kensuke

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 5 Pages, 2015/05

A CONTAIN-LMR code has been developed in JAEA for application to PRA of LMFRs since the original CONTAIN code had been introduced from SNL of U.S. in 1982. The code is a best-estimate, integrated analysis tool for predicting the physical, chemical and radiological conditions inside a containment building of LMFRs following a severe accident with reactor vessel melt-through. The code is also able to predict the source term to the environment in the accident. This code can treat many important phenomena consistently such as sodium fire, radioactive aerosol behavior, hydrogen burn, sodium-concrete reaction and core debris-concrete interaction occurred in the accident with inter-cell heat and mass flow under the multiple cell geometry. This paper describes the chronology of the code development in JAEA briefly as an introduction, and after that, the outline of computational models in the code, the examples of the code validation, and the future plan of the code application are described.

JAEA Reports

Design study for thermal insulation method of submerged piping

Saito, Kazuo*; Kusunoki, Tsuyoshi; Ishida, Toshihisa

JAERI-Tech 2001-038, 100 Pages, 2001/06

JAERI-Tech-2001-038.pdf:6.02MB

no abstracts in English

JAEA Reports

Surveillance system for radiation monitoring in HTTR

Nakazawa, Takashi; Kikuchi, Hisaki; Yasu, Katsuji; Yoshino, Toshiaki; Ashikagaya, Yoshinobu; Sato, Koichi; Minowa, Yuji; Nomura, Toshibumi

JAERI-Tech 2001-010, 125 Pages, 2001/03

JAERI-Tech-2001-010.pdf:7.4MB

no abstracts in English

JAEA Reports

Radiation monitoring for the HTTR rise-to-power test (1) and (2)'

Nakazawa, Takashi; Yoshino, Toshiaki; Yasu, Katsuji; Ashikagaya, Yoshinobu; Kikuchi, Hisaki

JAERI-Tech 2001-001, 101 Pages, 2001/02

JAERI-Tech-2001-001.pdf:5.15MB

no abstracts in English

JAEA Reports

Study of integrated structure of mercury target container with safety hull

Kaminaga, Masanori; Terada, Atsuhiko*; Haga, Katsuhiro; Kinoshita, Hidetaka; Ishikura, Shuichi*; Hino, Ryutaro

JAERI-Tech 2000-076, 70 Pages, 2001/01

JAERI-Tech-2000-076.pdf:4.01MB

no abstracts in English

Journal Articles

Pressure oscillation due to discharge of high-temperature and high-pressure water into pool water

Kusunoki, Tsuyoshi; Ito, Toshio*; Nariai, Hideki*

Nippon Kikai Gakkai 2000-Nendo Nenji Taikai Koen Rombunshu, p.645 - 646, 2000/08

no abstracts in English

JAEA Reports

None

Kishida, Masako*; *; *

PNC-TJ3678 98-001, 206 Pages, 1998/03

PNC-TJ3678-98-001.pdf:5.53MB

no abstracts in English

Journal Articles

A Proposal for accident management optimization based on the study of accident sequence analysis for a BWR

Sobajima, Makoto

IAEA-TECDOC-1002, p.27 - 36, 1998/03

no abstracts in English

Journal Articles

In order to realize a nuclear ship

Fune No Kagaku, 51(1), p.68 - 74, 1998/01

no abstracts in English

Journal Articles

Basical experiment on pressure behavior in a water-filled containment vessel during a loss of coolant accident

Kusunoki, Tsuyoshi; Yoritsune, Tsutomu; Ishida, Toshihisa

Nippon Genshiryoku Gakkai-Shi, 40(2), p.135 - 143, 1998/00

 Times Cited Count:1 Percentile:83.29(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Analysis of core flooding capability and containment vessel pressure during LOCA on advanced marine reactor MRX

Kusunoki, Tsuyoshi; *; Yoritsune, Tsutomu; ; Ishida, Toshihisa

JAERI-Tech 97-046, 56 Pages, 1997/09

JAERI-Tech-97-046.pdf:1.88MB

no abstracts in English

JAEA Reports

None

PNC-TN1410 97-031, 638 Pages, 1997/08

PNC-TN1410-97-031.pdf:12.12MB

no abstracts in English

JAEA Reports

None

Yamaguchi, Takashi

PNC-TN1410 97-028, 14 Pages, 1997/07

PNC-TN1410-97-028.pdf:0.28MB

no abstracts in English

Journal Articles

Guidance for the use of PSA level-2 analysis for improving containment performance

Sobajima, Makoto

Nippon Genshiryoku Gakkai-Shi, 39(7), p.560 - 562, 1997/00

no abstracts in English

JAEA Reports

A study for leak testing in the fuel handling facility "JOYO"

Ito, Hideaki; ; ;

PNC-TN9410 96-298, 177 Pages, 1996/11

PNC-TN9410-96-298.pdf:4.81MB

The fuel handling facility in "JOYO" must maintain an argon atmosphere and be gas tight; this prevents the oxidation of sodium adhering to a fuel assembly and leakage of radioactive gases. Periodic leak testing of the double O-ring gas seal had been performed at increasing pressure to assure its specified leak tightness. The problem with this method was that it took a long time to obtain an accurate measurement. The leak testing methods for the fuel handling facility, the reactor containment vessel, and other vessels were all reexamined. As a consequence, it was determined that alternative devices and methods for improving the leak rate measurements should be studied. Four methods of leak testing were evaluated; the present increasing pressure method, helium leak testing, decreasing pressure method, and a liquid nitrogen decreasing pressure method. A new automatic leak measurement device was used in these evaluations. The results of the utilization and limitations of the four methods of leak testing are summarized as follows. (1) The decreasing pressure leak testing method was efficient with regard to accuracy and stability for use in the fuel handling facility. (2) The automatic leak measurement device used a statistical calculation to measure the leak rate stability and it met the specified measurement requirements. (3) The leak rate measuring time was reduced by half with this new device and it could also simultaneously examine other objects.

Journal Articles

Analytical study on depressurization during PWR station blackout

Hidaka, Akihide; Ezzidi, A.*; Sugimoto, Jun

PSA 96: Int. Topical Meeting on Probabilistic Safety Assessment, 3, p.1548 - 1556, 1996/00

no abstracts in English

JAEA Reports

None

*; *; *

PNC-TJ2678 95-007, 134 Pages, 1995/03

PNC-TJ2678-95-007.pdf:4.2MB

None

116 (Records 1-20 displayed on this page)