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Journal Articles

Ten years after the NPP accident at Fukushima; Review on fuel debris behavior in contact with water

Grambow, B.; Nitta, Ayako; Shibata, Atsuhiro; Koma, Yoshikazu; Utsunomiya, Satoshi*; Takami, Ryu*; Fueda, Kazuki*; Onuki, Toshihiko*; Jegou, C.*; Laffolley, H.*; et al.

Journal of Nuclear Science and Technology, 59(1), p.1 - 24, 2022/01

 Times Cited Count:15 Percentile:71.66(Nuclear Science & Technology)

Journal Articles

Selective removal of radiocesium from micaceous clay for post-accident soil decontamination by temperature-controlled Mg-leaching in a column

Yin, X.; Zhang, L.*; Meng, C.*; Inaba, Yusuke*; Wang, X.*; Nitta, Ayako; Koma, Yoshikazu; Takeshita, Kenji*

Journal of Hazardous Materials, 387, p.121677_1 - 121677_10, 2020/04

 Times Cited Count:12 Percentile:54.1(Engineering, Environmental)

Journal Articles

Study on explosion characteristics of natural gas and methane in semi-open space for the HTTR hydrogen production system

Inaba, Yoshitomo; Nishihara, Tetsuo; Groethe, M. A.*; Nitta, Yoshikazu*

Nuclear Engineering and Design, 232(1), p.111 - 119, 2004/07

 Times Cited Count:26 Percentile:82.77(Nuclear Science & Technology)

It is important to grasp the explosion characteristics of object gases: natural gas and methane, in order to evaluate the influence of a gas explosion accident in the HTTR hydrogen production system on the reactor. Thus, we carried out explosion experiments of the object gases in semi-open space, and verified a numerical analysis code for the simulation of the explosion accident. It was confirmed that NG-air mixture or methane-air mixture in semi-open space didn't result in DDT although 10 g of C-4 explosive was used as an ignition source, and the numerical results agreed relatively with the experimental results. As a result, we could have the prospects for predicting the influence of the explosion accident on the reactor.

Journal Articles

Analytical study on fire and explosion accidents assumed in HTGR hydrogen production system

Inaba, Yoshitomo; Nishihara, Tetsuo; Nitta, Yoshikazu*

Nuclear Technology, 146(1), p.49 - 57, 2004/04

 Times Cited Count:4 Percentile:29.26(Nuclear Science & Technology)

One of the most important safety design issues for a hydrogen production system coupling with a High Temperature Gas-cooled Reactor (HTGR) is to ensure reactor safety against fire and explosion accidents because a large amount of combustible fluid is dealt with in the system. The Japan Atomic Energy Research Institute (JAERI) has a demonstration test plan of a hydrogen production system by steam reforming of methane coupling with the High Temperature engineering Test Reactor (HTTR). In the plan, we developed the P2A code system to analyze event sequences and consequences in detail on the fire and explosion accidents assumed in the HTGR or HTTR hydrogen production system. This paper described the three accident scenarios assumed in the system, the structure of P2A, the analysis procedure with P2A and the results of the numerical analyses based on the accident scenarios, and it was showed that P2A was a useful tool for the accident analysis in the system.

Oral presentation

Database for analytical data of radioactive wastes originated from the accident in Fukushima Daiichi Nuclear Power Station

Nitta, Ayako; Oki, Keiichi; Koma, Yoshikazu

no journal, , 

Various radioactive wastes generated in Fukushima Daiichi Nuclear Power Station should be safely disposed of. The properties of the wastes are required to understand. For that, the wastes are sampled and performed analyses. To utilize obtained analytical data, the database "FRAnDLi" was made to provide the data through the Internet.

Oral presentation

Oral presentation

Investigation of the radionuclide transfer based on the radiochemical analysis of the genuine samples at Fukushima Daiichi NPS site, 1; Research for actinide transfer to secondly waste from water treatment

Murakami, Erina; Oki, Keiichi; Takahatake, Yoko; Nitta, Ayako; Shibata, Atsuhiro; Koma, Yoshikazu

no journal, , 

no abstracts in English

Oral presentation

Study on the radioactive contamination in the reactor building unit #4 of Fukushima Daiichi NPS

Nitta, Ayako; Hinai, Hiroshi; Shibata, Atsuhiro; Nomura, Kazunori; Oki, Keiichi; Koma, Yoshikazu

no journal, , 

Oral presentation

Investigation of the radionuclide transfer based on the radiochemical analysis of the genuine samples at Fukushima Daiichi NPS site, 7; Actinide nuclides in the contaminated water

Hinai, Hiroshi; Nitta, Ayako; Shibata, Atsuhiro; Koma, Yoshikazu; Kaneko, Masaaki*; Ichikawa, Masashi*

no journal, , 

no abstracts in English

Oral presentation

Radiochemical analysis of actual samples collected at the Fukushima Daiichi NPS site

Ichikawa, Masashi*; Kaneko, Masaaki*; Koma, Yoshikazu; Hinai, Hiroshi; Nitta, Ayako; Shibata, Atsuhiro

no journal, , 

To study on treatment and disposal of solid waste generated at Fukushima Daiichi NPS (1F), radionuclide composition of sample taken from the bottom of primary containment vessel (PCV) of unit 1 was acquired by radioactivity analysis. It was the first time that nuclide composition data of samples taken from the inside of the reactor had been acquired, and the acquisition of these data will make it possible to estimate the origin of contaminants.

Oral presentation

Investigation of the radionuclide transfer based on the radiochemical analysis of the genuine samples at Fukushima Daiichi NPS site, 5; Estimation method of the origin of contamination in the reactor

Kaneko, Masaaki*; Ichikawa, Masashi*; Hinai, Hiroshi; Nitta, Ayako; Shibata, Atsuhiro; Koma, Yoshikazu

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Characterization of radioactive samples at Fukushima Daiichi NPS site, 2; Radiochemical analysis of spent activated carbon adsorbents in Multiple Radio-nuclides Removal System

Nitta, Ayako; Hinai, Hiroshi; Ichige, Yoshiaki; Koma, Yoshikazu; Shibata, Atsuhiro

no journal, , 

no abstracts in English

Oral presentation

Analysis of alpha radionuclide in the contaminated water at the torus room of unit #2 reactor of Fukushima Daiichi NPS, 1; Outline of the state analysis of alpha radionuclides containing in the solid component

Kitatsuji, Yoshihiro; Ouchi, Kazuki; Yomogida, Takumi; Oka, Toshitaka; Nitta, Ayako; Hinai, Hiroshi; Koma, Yoshikazu; Konno, Katsuhiro*

no journal, , 

In order to clarify the chemical species of alpha nuclides in the contaminated water of the Fukushima Daiichi Nuclear Power Station, sludge was classified by particle size. The concentration of alpha radioisotope was measured and the particles were investigated. Most alpha particles were larger than 10 micrometers and settled at the bottom of the torus chamber.

Oral presentation

Oral presentation

$$alpha$$-emitting nuclides analysis of the stagnant water including sediments in Fukushima Daiichi NPS, 6; Chemical state analysis of $$alpha$$-emitting nuclide particles obtained from unit #3 stagnant water sludge (Part 2)

Nitta, Asahi; Usui, Akane; Yamaguchi, Yukako; Sekio, Yoshihiro; Maeda, Koji; Koma, Yoshikazu; Konno, Katsuhiro*

no journal, , 

no abstracts in English

Oral presentation

$$alpha$$-emitting nuclides analysis of the stagnant water including sediments in Fukushima Daiichi NPS, 8; Behavior of moving to sediment of Pu and Am

Nitta, Ayako; Hinai, Hiroshi; Kitawaki, Shinichi; Koma, Yoshikazu

no journal, , 

no abstracts in English

19 (Records 1-19 displayed on this page)
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