Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 23

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Removal of soluble strontium via incorporation into biogenic carbonate minerals by halophilic bacterium Bacillus sp. strain TK2d in a highly saline solution

Horiike, Takumi*; Dotsuta, Yuma*; Nakano, Yuriko*; Ochiai, Asumi*; Utsunomiya, Satoshi*; Onuki, Toshihiko; Yamashita, Mitsuo*

Applied and Environmental Microbiology, 83(20), p.e00855-17_1 - e00855-17_11, 2017/10

 Times Cited Count:14 Percentile:59.31(Biotechnology & Applied Microbiology)

Radioactive strontium ($$^{90}$$Sr) leaked into the ocean from the Fukushima Daiichi Nuclear Power Plant after the nuclear accident. Since the removal of Sr using general adsorbents is not efficient at high salinity, this study investigated removal of soluble Sr from a saline solution by biogenic carbonate minerals. An isolate, Bacillus sp. strain TK2d, from marine sediment removed more than 99 % of Sr in a saline solution. Sr adsorbed at the cell surface and then carbonate minerals containing Sr developed outside the cells.

JAEA Reports

Chemical composition of artificial seawater after leaching tests of irradiated fuel

Tanaka, Kosuke; Suto, Mitsuo; Onishi, Takashi; Akutsu, Yoko; Yoshitake, Tsunemitsu; Yamashita, Shinichiro; Sekioka, Ken*; Ishigamori, Toshio*; Obayashi, Hiroshi; Koyama, Shinichi

JAEA-Research 2013-036, 31 Pages, 2013/12

JAEA-Research-2013-036.pdf:3.31MB

In the accident of Fukushima Daiichi NPPs, the water ingress was performed in order to decrease the reactor temperature. At that time, sea water was temporarily used as a coolant and the water contacted with nuclear fuel directly. It can be supposed that fission products (FP) were easily migrated from the fuel to sea water in this situation and that affect the water quality. The knowledge of leaching behavior, therefore, is necessary for evaluating the integrity of reactor component materials such as steels for pressure containment vessel and for reactor vessel. In order to obtain the fundamental knowledge for leaching behavior of FP in the hot sea water, the leaching tests of irradiated fuel were performed and the leachates were subjected to chemical analysis. It is found that he leaching rate of each nuclides obtained in this study were similar to that of the leaching results simulating the underground water.

Journal Articles

Annular core experiments in HTTR's start-up core physics tests

Fujimoto, Nozomu; Yamashita, Kiyonobu*; Nojiri, Naoki; Takeuchi, Mitsuo; Fujisaki, Shingo; Nakano, Masaaki*

Nuclear Science and Engineering, 150(3), p.310 - 321, 2005/07

 Times Cited Count:6 Percentile:40.53(Nuclear Science & Technology)

Annular cores were formed in startup-core-physics tests of the High Temperature Engineering Test Reactor (HTTR) to obtain experimental data for verification of calculation codes. The first criticality, control rod positions at critical conditions, neutron flux distribution, excess reactivity etc. were measured as representative data. These data were evaluated with Monte Carlo code MVP that can consider the heterogeneity of coated fuel particles (CFP) distributed randomly in fuel compacts directly. It was made clear that the heterogeneity effect of CFP on reactivity for annular cores is smaller than that for fully-loaded cores. Measured and calculated effective multiplication factors (k) were agreed with differences less than 1%$$Delta$$k. Measured neutron flux distributions agreed with calculated results. The revising method was applied for evaluation of excess reactivity to exclude negative shadowing effect of control rods. The revised and calculated excess reactivity agreed with differences less than 1%$$Delta$$k/k.

Journal Articles

Start up core physics tests of High Temperature Engineering Test Reactor (HTTR), 2; First criticality by an annular form fuel loading and its criticality prediction method

Fujimoto, Nozomu; Nakano, Masaaki*; Takeuchi, Mitsuo; Fujisaki, Shingo; Yamashita, Kiyonobu

Nihon Genshiryoku Gakkai-Shi, 42(5), p.458 - 464, 2000/05

 Times Cited Count:6 Percentile:42.69(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Startup core physics tests of High Temperature Engineering Test Reactor (HTTR), 1; Test plan, fuel loading and nuclear characteristics tests

Yamashita, Kiyonobu; Fujimoto, Nozomu; Takeuchi, Mitsuo; Fujisaki, Shingo; Nakano, Masaaki*; Umeta, Masayuki; Takeda, Takeshi; Mogi, Haruyoshi; Tanaka, Toshiyuki

Nihon Genshiryoku Gakkai-Shi, 42(1), p.30 - 42, 2000/01

 Times Cited Count:3 Percentile:26.46(Nuclear Science & Technology)

no abstracts in English

Journal Articles

First criticality prediction of the HTTR by 1/M interposition method

Fujimoto, Nozomu; Nakano, Masaaki*; Nojiri, Naoki; Takeuchi, Mitsuo; Fujisaki, Shingo; Yamashita, Kiyonobu

JAERI-Conf 99-006, p.328 - 333, 1999/08

no abstracts in English

Journal Articles

Measurement of control rod reactivity worth with long insertion time by inverse kinetics rod drop method

Yamashita, Kiyonobu; Takeuchi, Mitsuo; Fujimoto, Nozomu; Fujisaki, Shingo; Nakano, Masaaki*; Nojiri, Naoki; Tamura, Seiji*

Nihon Genshiryoku Gakkai-Shi, 41(1), p.35 - 38, 1999/00

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Results of HTTR criticality tests

Fujimoto, Nozomu; Takeuchi, Mitsuo; Fujisaki, Shingo; Nakano, Masaaki*; Yamashita, Kiyonobu; Mogi, Haruyoshi

UTNL-R-0378, p.5.1 - 5.10, 1999/00

no abstracts in English

JAEA Reports

Preliminary analyses for HTTR's start-up physics tests by Monte Carlo code MVP

Nojiri, Naoki; Nakano, Masaaki; Ando, Hiroei; Fujimoto, Nozomu; Takeuchi, Mitsuo; Fujisaki, Shingo; Yamashita, Kiyonobu

JAERI-Tech 98-032, 59 Pages, 1998/08

JAERI-Tech-98-032.pdf:2.48MB

no abstracts in English

JAEA Reports

Preliminary analyses for HTTR's start-up physics tests by HTTR nuclear characteristics evaluation code system

Fujimoto, Nozomu; Nojiri, Naoki; Nakano, Masaaki*; Takeuchi, Mitsuo; Fujisaki, Shingo; Yamashita, Kiyonobu

JAERI-Tech 98-021, 66 Pages, 1998/06

JAERI-Tech-98-021.pdf:2.63MB

no abstracts in English

JAEA Reports

Analytical estimation of control rod shadowing effect for excess reactivity measurement of high temperature engineering test reactor (HTTR)

Nakano, Masaaki; Yamashita, Kiyonobu; Fujimoto, Nozomu; Nojiri, Naoki; Takeuchi, Mitsuo; Fujisaki, Shingo; *; Nakata, Tetsuo*

JAERI-Tech 98-017, 61 Pages, 1998/05

JAERI-Tech-98-017.pdf:2.68MB

no abstracts in English

Journal Articles

Benchmark problems of start-up core physics of High Temperature engineering Test Reactor (HTTR)

Yamashita, Kiyonobu; Nojiri, Naoki; Fujimoto, Nozomu; Nakano, Masaaki*; Ando, Hiroei; Nagao, Yoshiharu; Nagaya, Yasunobu; Akino, Fujiyoshi; Takeuchi, Mitsuo; Fujisaki, Shingo; et al.

Proc. of IAEA TCM on High Temperature Gas Cooled Reactor Applications and Future Prospects, p.185 - 197, 1998/00

no abstracts in English

JAEA Reports

Integrity assessment of test fuel assemblies of the High Temperature Engineering Test Reactor

Hayashi, Kimio; Shiozawa, Shusaku; Fukuda, Kosaku; Tsuruta, Harumichi; Ikawa, Katsuichi; *; ; Tobita, Tsutomu; Shiratori, Tetsuo; Akabori, Mitsuo; et al.

JAERI-M 90-115, 77 Pages, 1990/07

JAERI-M-90-115.pdf:2.65MB

no abstracts in English

JAEA Reports

Test and research ice-blasting equipment, II

Nishimoto, Wataru*; Kimuro, Harumi*; Ishibashi, Seijiro*; Miyahara, Shuji*; Yamashita, Saburo*; Hayashi, Mitsuo*; Suzuki, Yoji*; Hirose, Yasuo*

PNC TJ118 85-06VOL2, 221 Pages, 1985/04

PNC-TJ118-85-06VOL2.pdf:20.84MB

None

JAEA Reports

Test and research of Ice-Blasting equipment, II

Nishimoto, Wataru*; Kimuro, Harumi*; Ishibashi, Seijiro*; Miyahara, Shuji*; Yamashita, Saburo*; Hayashi, Mitsuo*; Suzuki, Yoji*; Hirose, Yasuo*

PNC TJ118 85-06VOL1, 21 Pages, 1985/04

PNC-TJ118-85-06VOL1.pdf:1.04MB

no abstracts in English

JAEA Reports

Design and research of ice-blasting equipment

Shimizu, Makoto*; Kimuro, Harumi*; Ayabe, Muneo*; Kouno, Yasumasa*; Miyahara, Shuji*; Yamashita, Saburo*; Kanazawa, Kazuo*; Hayashi, Mitsuo*; Yoshizaki, Masato*

PNC TJ118 83-05VOL2, 222 Pages, 1984/03

PNC-TJ118-83-05VOL2.pdf:14.66MB

None

JAEA Reports

Design and research of ice-blasting equipment

Shimizu, Makoto*; Kimuro, Harumi*; Ayabe, Muneo*; Kouno, Yasumasa*; Miyahara, Shuji*; Yamashita, Saburo*; Kanazawa, Kazuo*; Hayashi, Mitsuo*; Yoshizaki, Masato*

PNC TJ118 83-05VOL1, 42 Pages, 1984/03

PNC-TJ118-83-05VOL1.pdf:1.06MB

None

JAEA Reports

Preparation and properties of B$$_{4}$$C for MK-2

Yamashita, Mitsuo*; Saruwatari, Mitsuyoshi*; Shigi, Tadasuke*; Nishikawa, Akira*; Hara, Masatsugu*

PNC TN251 75-21, 40 Pages, 1975/05

PNC-TN251-75-21.pdf:1.97MB

Boron carbide pellets (B$$_{4}$$C pellets), having 90% relative density, were experimentally fabricated and characterized to be applied to the control rods of the experimental fast reactor "JOYO" MK-II. Raw B$$_{4}$$C pellets were hot-pressed from natural B$$_{4}$$C powder and then finished pellets were prepared by burnishing them to adjust their dimensions. Their dimensions, weights, densities, X-ray diffraction patterns, microscopies, chemical compositions and adsorbed gases were measured. Finished B$$_{4}$$C pellets are concluded to satisfy their requirements such as dimension, weight, density, chemical composition and impurity levels. However, density was presumed to be heterogeneous inside pellets, since heterogeneous distribution of pore was observed under microscope.

Oral presentation

Development of flexible fuel cycle initiative, 3; Uranium removal

Yamashita, Junichi*; Fukasawa, Tetsuo*; Kawamura, Fumio*; Hoshino, Kuniyoshi*; Sasahira, Akira*; Minato, Kazuo; Akabori, Mitsuo; Arai, Yasuo

no journal, , 

no abstracts in English

Oral presentation

Chemical composition of artificial seawater after immersion tests of irradiated fuel

Tanaka, Kosuke; Suto, Mitsuo; Onishi, Takashi; Akutsu, Yoko; Obayashi, Hiroshi; Koyama, Shinichi; Yoshitake, Tsunemitsu; Yamashita, Shinichiro; Sekioka, Ken*; Ishigamori, Toshio*

no journal, , 

Chemical analysis of artificial seawater after immersion tests of irradiated fuel was carried out.

23 (Records 1-20 displayed on this page)