Carbonated nanohydroxyapatite from bone waste and its potential as a super adsorbent for removal of toxic ions

Sekine, Yurina; Nankawa, Takuya; Yamada, Teppei*; Matsumura, Daiju; Nemoto, Yoshihiro*; Takeguchi, Masaki*; Sugita, Tsuyoshi; Shimoyama, Iwao; Kozai, Naofumi; Morooka, Satoshi

Journal of Environmental Chemical Engineering, 9(2), p.105114_1 - 105114_12, 2021/04

https://doi.org/10.1016/j.jece.2021.105114

Remediating toxic ion contamination is crucial for protecting human health and the environment. This study aimed to provide a powerful strategy for effectively utilizing bone waste from the food production and preparation industries for removal of toxic ions. Here, we show that immersing pig bone in NaHCO solution produced a carbonated nanohydroxyapatites (C-NHAP). The C-NHAP exhibited high adsorptivity for Sr, Cd, Pb, and Cu. The strontium adsorptivity was about 250 and 4,500 times higher than that of normal bone and synthetic HAP, respectively. The C-NHAP is an eco-friendly, high-performance material that is simple to prepare and should be useful for tackling problems of food waste disposal and environmental pollution.

Study on loss-of-cooling and loss-of-coolant accidents in spent fuel pool, 6; Analysis on oxidation behavior of fuel cladding tubes by the SAMPSON code

Morita, Yoshihiro*; Suzuki, Hiroaki*; Naito, Masanori*; Nemoto, Yoshiyuki; Kaji, Yoshiyuki

Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 9 Pages, 2019/05

In this study, the SAMPSON code was modified to evaluate severe accidents in a spent fuel pool (SFP). Not only the SFP but also upper spaces of the SFP, walls of the reactor building, and the blowout panel were included. Air oxidation models obtained by the Zircaroy-4 cladding (ANL model) and the Zircaroy-2 cladding (JAEA model) were included in the modified SAMPSON code. Experiments done by Sandia National Laboratory using simulated fuel assemblies equivalent to those of an actual BWR plant were analyzed by the modified SAMPSON code to confirm the functions for analysis of the severe SFP accidents.

Nuclear Facilities Management Section Mutsu Office, Aomori Research and Development Center operations report; FY 2012&2013

Tajima, Yoshihiro; Kuwabara, Jun; Oyokawa, Atsushi; Kabuto, Shoji; Araya, Naoyuki; Kikuchi, Kaoru; Miyamoto, Shingo; Nemoto, Hideyuki; Oe, Osamu

JAEA-Review 2016-003, 56 Pages, 2016/05

JAEA-Review-2016-003.pdf:7.16MB

Nuclear Facilities Management Section implements the operation, maintenance and decommissioning of the first nuclear ship "MUTSU" and the operation and maintenance of the liquid waste facility and the solid waste facility where a small amount of nuclear fuel is used. This is the report on the operations of the Nuclear Facilities Management Section for FY 2012 and FY 2013.

Application of the two-electron transfer reaction to helium ion density and energy distribution measurements in JT-60

Tobita, Kenji; Kusama, Yoshinori; Nakamura, Hiroo; Ito, Takao; Tsukahara, Yoshimitsu; Nemoto, Masahiro; Kubo, Hirotaka; Takeuchi, Hiroshi; Kuriyama, Masaaki; Matsuoka, Mamoru; et al.

Nuclear Fusion, 31(5), p.956 - 960, 1991/00

https://doi.org/10.1088/0029-5515/31/5/013

no abstracts in English

Calibration of active beam scattering system and its application of JT-60

Tobita, Kenji; Kusama, Yoshinori; Nemoto, Masahiro; Takeuchi, Hiroshi; Ito, Takao; Tsukahara, Yoshimitsu; Shitomi, Morimasa; Watanabe, Kazuhiro; Ohara, Yoshihiro

Kaku Yugo Kenkyu, 59(SPECIAL ISSUE), p.139 - 156, 1988/00

no abstracts in English

Development of reactivity feedback effect measurement techniques under sub-critical condition in fast reactor, 1-1; Purpose and program

Okajima, Shigeaki; Nishi, Hiroshi; Yamane, Yoshihiro*; Kanemoto, Shigeru*; Yamane, Tsuyoshi; Mori, Takamasa; Kitamura, Yasunori; Fukushima, Masahiro; Kitano, Akihiro; Ando, Masaki; et al.

no journal, , 

The program was planned and has been carried out to develop of the reactivity feedback effect measurement techniques under sub-critical condition in the start-up experiment for fast reactors. The program includes the demonstration of the developed technique in fast critical assembly (FCA) and the proposal of the appropriate measurement system based on the results. The background and the purposes of the program and the outline of development subjects are presented.

Evaluation of Cesium accumulating ability in M2 generation of Amaranthus irradiated with ion beams

Nemoto, Kazuhiro*; Minami, Mineo*; Matsushima, Kenichi*; Tsurukawa, Akiko*; Kinoshita, Junichi*; Hase, Yoshihiro

no journal, , 

no abstracts in English

Study on improvement of safety for accident conditions in spent fuel pool, 12; Loss of coolant accident analysis by improved SAMPSON code

Morita, Yoshihiro*; Suzuki, Hiroaki*; Naito, Masanori*; Nemoto, Yoshiyuki; Kaji, Yoshiyuki

no journal, , 

A new model including the spent fuel pool (SFP) or Zr oxidation behavior which is necessary to evaluate the SFP accident caused by cooling function loss was developed and implanted in the severe accident code SAMPSON in this work. Results of the evaluation using the improved code will be presented.

In situ transmission electron microscopy observation of melted germanium sandwiched by multilayer graphenes

Suzuki, Seiya; Nemoto, Yoshihiro*; Shiiki, Natsumi*; Nakayama, Yoshiko*; Takeguchi, Masaki*

no journal, ,