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JAEA Reports

Stabilization of MOX dissolving solution at STACY

Kobayashi, Fuyumi; Sumiya, Masato; Kida, Takashi; Kokusen, Junya; Uchida, Shoji; Kaminaga, Jota; Oki, Keiichi; Fukaya, Hiroyuki; Sono, Hiroki

JAEA-Technology 2016-025, 42 Pages, 2016/11

JAEA-Technology-2016-025.pdf:17.88MB

A preliminary test on MOX fuel dissolution for the STACY critical experiments had been conducted in 2000 through 2003 at Nuclear Science Research Institute of JAEA. Accordingly, the uranyl / plutonium nitrate solution should be reconverted into oxide powder to store the fuel for a long period. For this storage, the moisture content in the oxide powder should be controlled from the viewpoint of criticality safety. The stabilization of uranium / plutonium solution was carried out under a precipitation process using ammonia or oxalic acid solution, and a calcination process using a sintering furnace. As a result of the stabilization operation, recovery rate was 95.6% for uranium and 95.0% for plutonium. Further, the recovered oxide powder was calcined again in nitrogen atmosphere and sealed immediately with a plastic bag to keep its moisture content low and to prevent from reabsorbing atmospheric moisture.

Journal Articles

Examination of analytical method of rare earth elements in used nuclear fuel

Ozawa, Mayumi; Fukaya, Hiroyuki; Sato, Makoto; Kamohara, Keiko*; Suyama, Kenya; Tonoike, Kotaro; Oki, Keiichi; Umeda, Miki

Proceedings of 53rd Annual Meeting of Hot Laboratories and Remote Handling Working Group (HOTLAB 2016) (Internet), 9 Pages, 2016/11

Journal Articles

Maintenance activities of instrumentation control device at JRR-3

Isaka, Koji; Terunuma, Noriaki; Ouchi, Satoshi; Oki, Keiichi; Suwa, Masayuki

Nihon Hozen Gakkai Dai-6-Kai Gakujutsu Koenkai Yoshishu, p.279 - 282, 2009/08

As the modified JRR-3 has been operated for 18 years, it is necessary to be maintained for keeping the safe and stable operation. The review of maintenance activity is constantly performed for the step-by-step update of facilities and the improvement of the maintenance method and so on. Our investigation of the maintenance activity about the instrumentation and control device of modified JRR-3 is presented.

JAEA Reports

Preparation of reference material for solidified products made from radioactive miscellaneous wastes by melting treatment; Reference material for solidified product containing $$alpha$$-ray emitting nuclides (Joint research)

Ishimori, Kenichiro; Oki, Keiichi; Takaizumi, Hirohide; Kameo, Yutaka; Oki, Yoshiyuki*; Nakashima, Mikio

JAEA-Technology 2007-065, 20 Pages, 2008/01

JAEA-Technology-2007-065.pdf:1.4MB

In order to prepare a reference material which is used for radiochemical analysis of solidified products made from non-metallic miscellaneous low level radioactive solid wastes by melting in Nuclear Science Research Institute, Japan Atomic Energy Agency, the preparation method of the reference material was investigated. Under the optimum melting conditions obtained in this report, the reference material containing $$^{237}$$Np, $$^{241}$$Am and $$^{244}$$Cm as $$alpha$$-ray emitting nuclides was successfully prepared. From radiochemical analysis of the reference material, the radioactive concentration of respective nuclides was determined to be 0.188$$pm$$0.001 Bq/g for $$^{237}$$Np, 0.368$$pm$$0.004 Bq/g for $$^{241}$$Am, 0.402$$pm$$0.010 Bq/g for $$^{244}$$Cm.

Oral presentation

Simplification of procedure for radiochemical analysis of solidified products, 5; Separation method for $$^{14}$$C

Ishimori, Kenichiro; Oki, Keiichi; Kameo, Yutaka; Takaizumi, Hirohide; Nakashima, Mikio; Oki, Yoshiyuki*; Isogai, Keisuke*

no journal, , 

no abstracts in English

Oral presentation

Clearance activities of concrete generated from modification of JRR-3, 2; Investigation of contamination situation of concrete

Tachibana, Mitsuo; Satoyama, Tomonori; Oki, Keiichi; Naito, Akira; Takaizumi, Hirohide; Yoshimori, Michiro; Okoshi, Minoru; Hoshi, Akiko

no journal, , 

no abstracts in English

Oral presentation

Clearance activities of concrete generated from modification of JRR-3, 3; Method for measurement and assessment of activity

Satoyama, Tomonori; Oki, Keiichi; Naito, Akira; Yoshimori, Michiro; Okoshi, Minoru; Kogure, Hiroto; Tsutsumi, Masahiro; Inanobe, Hiroshi

no journal, , 

no abstracts in English

Oral presentation

Clearance activities of concrete generated from modification of JRR-3, 1; Over view

Yoshimori, Michiro; Satoyama, Tomonori; Oki, Keiichi; Naito, Akira; Okoshi, Minoru; Hoshi, Akiko

no journal, , 

no abstracts in English

Oral presentation

Status of reduced enrichment program for research reactors in Japan

Oki, Keiichi; Murayama, Yoji; Sasajima, Fumio; Izumo, Hironobu; Inoue, Takeshi; Unesaki, Hironobu*

no journal, , 

no abstracts in English

Oral presentation

Detailed inspection of samples taken from un-irradiated fuel assembly at 1F4, 1; Outline of inspected samples and inspection methods

Motooka, Takafumi; Endo, Shinya; Sonoda, Takashi; Oki, Keiichi; Uehara, Hiroyuki; Obata, Hiroki; Tsukada, Takashi

no journal, , 

no abstracts in English

Oral presentation

Replacement of diffusers on JRR-3 secondary cooling tower

Imahashi, Masaki; Oba, Toshinobu; Oki, Keiichi; Suzuki, Makoto; Hayashi, Kazuhiko

no journal, , 

no abstracts in English

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

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

Characterization of radioactive samples at Fukushima Daiichi NPS site, 1; Radiochemical analysis of precipitate generated by contaminated water treatment

Hinai, Hiroshi; Oki, Keiichi; Koma, Yoshikazu; Shibata, Atsuhiro

no journal, , 

no abstracts in English

Oral presentation

Study on analysis planning for the rubble from the reactor buildings; Study on analysis planning for the rubble from the reactor buildings

Akimoto, Maya; Horita, Takuma; Nagai, Anna; Oki, Keiichi; Pyke, C.*; Hiller, P.*; Koma, Yoshikazu

no journal, , 

We investigated the planning method for analysis consistent with the characteristics of the Fukushima Daiichi NPS Wastes (1F wastes), and suggested that the method combining the Data Quality Objectives (DQO) process, which is widely adopted in environmental remediation, and the Bayesian inference, is effective. To evaluate the applicability of the method to the 1F waste, we tried to apply the method by setting the objective to classify rubble, which has large individual differences and diverse properties. In this study, we calculated the sample size required to determine the classification by difference of contamination by alpha nuclides for the rubble collected from the reactor buildings. We report on analysis planning for the rubble from the reactor buildings using the DQO process and the Bayesian inference.

Oral presentation

A Study of statistical planning method for analysis consistent with the characteristics of the Fukushima Daiichi NPS Wastes; Study on analysis planning for the sludge generated from the decontamination device

Nagai, Anna; Horita, Takuma; Akimoto, Maya; Oki, Keiichi; Hiller, P.*; Pyke, C.*; Koma, Yoshikazu

no journal, , 

We investigated the planning method for analysis consistent with the characteristics of the Fukushima Daiichi NPS Wastes (1F wastes), and suggested that the method combining the Data Quality Objectives (DQO) process and the Bayesian inference, is effective. To investigate the usefulness of the method, it was applied to the study of the analysis plan for 1F wastes. In this study, we assume the case of disposal of the sludge generated from the decontamination device, and discussed for the method with the objective of understanding the properties necessary for disposal. The sludge was assumed that after dewatering temporarily stored and then stabilization and sample size calculated considering the change in population due to the dewatering. We report on the study on analysis planning for the sludge generated from the decontamination device using the DQO process and the Bayesian inference.

Oral presentation

A Study of statistical planning method for analysis consistent with the characteristics of the Fukushima Daiichi NPS Wastes, 2; Calculation of the optimal sample size using the Bayesian inference

Horita, Takuma; Akimoto, Maya; Nagai, Anna; Oki, Keiichi; Pyke, C.*; Hiller, P.*; Koma, Yoshikazu

no journal, , 

In order to streamline the characterization of radioactive wastes generated by the decommissioning of the Fukushima Daiichi Nuclear Power Station (1F) for the treatment and disposal, we are considering an efficient planning method for analysis. The planning method is combined the Data Quality Objectives Process (DQO process), which defines the quality control method for collecting environmental analysis data, and the Bayesian inference, which is a statistical method. Calculations using the Bayesian inference allow us to probabilistically evaluate the sample size required to obtain the desired results. In other words, unlike conventional tests conducted with frequency statistics, the sample size can be obtained along with the probability, and thus the sample size can be flexibly planned based on the probability. In this presentation, we will report on a method for calculating the sample size for two purposes: (1) comparison with the reference value for disposal, and (2) population classification according to disposal properties.

22 (Records 1-20 displayed on this page)