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Toyoda, Shin*; Inoue, Kazuhiko*; Yamaguchi, Ichiro*; Hoshi, Masaharu*; Hirota, Seiko*; Oka, Toshitaka; Shimazaki, Tatsuya*; Mizuno, Hideyuki*; Tani, Atsushi*; Yasuda, Hiroshi*; et al.
Radiation Protection Dosimetry, 199(14), p.1557 - 1564, 2023/09
Times Cited Count：0 Percentile：0.01(Environmental Sciences)Interlaboratory comparison studies are important for radiation dosimetry in order to demonstrate how the technique is universally available. The set of standard samples are examined in each participating laboratory in the present study. After a set of standard samples together with the samples with unknown doses, which were prepared in the same laboratory as the standard samples, are measured at a participating laboratory, those samples are sent to another participating laboratory for next measurement. There is some small difference observed in the sensitivity (the slope of the dose response line) of the standard samples while the differences in the obtained doses for the samples with unknown doses are rather systematic, implying that the difference is mostly due to the samples but not to measurements.
Oki, Shigeo; Sato, Isamu; Mizuno, Tomoyasu; Hayashi, Hideyuki; Tanaka, Kenya
Proceedings of International Conference on Advanced Nuclear Fuel Cycles and Systems (Global 2007) (CD-ROM), p.1280 - 1288, 2007/09
Uto, Nariaki; Okano, Yasushi; Naganuma, Masayuki; Mizuno, Tomoyasu; Hayashi, Hideyuki
JAEA-Research 2006-060, 68 Pages, 2006/09
JAEA-Research-2006-060.pdf:3.98MB
A design study on "Long-life Type Concept" of a 50MWe sodium-cooled metal-fueled reactor core was performed with more emphasis on irradiation results regarding fuel smear density. The concept aims at no refueling in a core life time, and achieving higher core outlet temperature such as 550
C which is advantageous to hydrogen production. The restriction of upper fuel smear density limit to 75% along with adjustments of fuel specifications showed feasibility of attaining core life time of 30 years and core outlet temperature of 550C. No indication of occurrence of absorber-cladding mechanical interaction (ACMI) was found in the evaluation of ACMI for a control rod element. A shielding with Zr-H was selected in view of enhancement of shielding performance, and the feasibility was shown to satisfy the target allowance level of the ratio of hydrogen to zirconium, more than 1.53, with PNC316 used as the cladding material.
Uto, Nariaki; Okano, Yasushi; Naganuma, Masayuki; Mizuno, Tomoyasu; Hayashi, Hideyuki
no journal, ,
This presents design study results on Long-life Type Concept for a sodium-cooled metal-fueled reactor core with 50MWe. The concept aims at no refueling and higher reactor outlet temperature which is advantageous to hydrogen production. It was found that the core life time of 30 years and the reactor outlet temperature of 550C can be attained by adjusting core and fuel specifications on condition that the fuel smear density is restricted within 75% with more emphasis on irradiation results. The design feasibility of durable control rod and radiation shielding was studied. No possibility of occurrence of absorber-cladding mechanical interaction was obtained on the analytical evaluation for a control rod element with B
C as absorber material. A shielding with Zr-H was selected in view of enhancement of shielding performance and core compactness, and the feasibility was shown to adequately restrict the amount of hydrogen permeation from the cladding to the allowable level.
Oki, Shigeo; Uto, Nariaki; Mizuno, Tomoyasu; Hayashi, Hideyuki; Tanaka, Kenya
no journal, ,
no abstracts in English
Todaka, Azumi*; Toyoda, Shin*; Tachi, Momoko*; Shimazaki, Tatsuya*; Oka, Toshitaka; Yamaguchi, Ichiro*; Inoue, Kazuhiko*; Yasuda, Hiroshi*; Hirota, Seiko*; Tani, Atsushi*; et al.
no journal, ,
To estimate the external exposure dose using electron spin resonance technique, we use a "standard sample" which were prepared at each laboratory with each preparation protocol. It is necessary to unite the preparation protocol for the "real" standard sample. In the point of view of the enamel extraction method, no difference was observed for five dose responses between the absorbed dose and the CO
radical intensity.
