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Role of retained austenite in low alloy steel at low temperature monitored by neutron diffraction

山下 享介; 諸岡 聡; Harjo, S.; 川崎 卓郎; 古賀 紀光*; 梅澤 修*

Scripta Materialia, 177, p.6 - 10, 2020/03

${it In situ}$ neutron diffraction measurements during tensile tests at low temperatures of a low alloy steel containing retained austenite have been performed. Evolutions of phase fractions and phase stresses were analyzed and discussed with the progress of deformation. The role of austenite in the steel during deformation at low temperatures was observed not to directly in the contribution to the strengths but in the improvement of the elongation by transformation of austenite to martensite -and in the increasing of the work-hardening rate by an increase in the phase fraction of martensite and the work hardening of martensite.


Effects of oxidation and secondary hydriding during simulated Loss-Of-Coolant-Accident tests on the bending strength of Zircaloy-4 fuel cladding tube

岡田 裕史; 天谷 政樹

Annals of Nuclear Energy, 136, p.107028_1 - 107028_9, 2020/02

In order to evaluate the fracture resistance of fuel rods against a seismic loading following a Loss-Of-Coolant-Accident (LOCA), the bending strength of fuel cladding which experienced a simulated LOCA has been investigated since the Fukushima-Daiichi Nuclear Power Plant accident. In this study, four-point-bending-tests were performed using Zircaloy-4 cladding tubes which experienced a simulated LOCA sequence in order to investigate the effects of oxidation and secondary hydriding occurring during a LOCA on the bending strength of fuel cladding. According to the obtained results, it was suggested that the maximum bending stress would be affected by the oxygen concentration in the prior-beta layer as well as the thickness of prior-beta layer. It was considered that the decrease in maximum bending stress by secondary hydriding is probably expressed by multiplying a factor of 0.37 by the maximum bending stress which solely takes account of the effect of oxidation.


Structure of superconducting Ca-intercalated bilayer Graphene/SiC studied using total-reflection high-energy positron diffraction

遠藤 由大*; 深谷 有喜; 望月 出海*; 高山 あかり*; 兵頭 俊夫*; 長谷川 修司*

Carbon, 157, p.857 - 862, 2020/02



Neutron transmission spectrum of liquid lead bismuth eutectic

大場 洋次郎; 伊藤 大介*; 齊藤 泰司*; 小野寺 陽平*; Parker, J. D.*; 篠原 武尚; 及川 健一

Materials Research Proceedings, Vol.15, p.160 - 164, 2020/02





JAEA-Review 2019-017, 182 Pages, 2020/01




3次元六角体系用中性子輸送計算コードの整備,2; MINISTRIコードの改良及び機能拡張

杉野 和輝; 滝野 一夫

JAEA-Data/Code 2019-011, 110 Pages, 2020/01




Conceptual study on a novel method for detecting nuclear material using a neutron source

米田 政夫; 藤 暢輔

Annals of Nuclear Energy, 135, p.106993_1 - 106993_6, 2020/01



Fracture limit of high-burnup advanced fuel cladding tubes under loss-of-coolant accident conditions

成川 隆文; 天谷 政樹

Journal of Nuclear Science and Technology, 57(1), p.68 - 78, 2020/01

 被引用回数:0 パーセンタイル:100(Nuclear Science & Technology)

To evaluate the fracture limit of high-burnup advanced fuel cladding tubes under loss-of-coolant accident (LOCA) conditions, laboratory-scale integral thermal shock tests were performed using the following advanced fuel cladding tubes with burnups of 73 - 85 GWd/t: M-MDA$textsuperscript{texttrademark}$, low-tin ZIRLO$textsuperscript{texttrademark}$, M5$textsuperscript{textregistered}$, and Zircaloy-2 (LK3). In total eight integral thermal shock tests were performed for these specimens, simulating LOCA conditions including ballooning and rupture, oxidation, hydriding, and quenching. During the tests, the specimens were oxidized to 10% - 30% equivalent cladding reacted (ECR) at approximately 1473 K and were quenched under axial restraint load of approximately 520 - 530 N. The effects of burnup extension and use of the advanced fuel cladding tubes on the ballooning and rupture, oxidation, and hydriding under LOCA conditions were inconsiderable. Further, the high-burnup advanced fuel cladding tube specimens did not fracture in the ECR values equal to or lower than the fracture limits of the unirradiated Zircaloy-4 cladding tube reported in previous studies. Therefore, it can be concluded that the fracture limit of fuel cladding tubes is not significantly reduced by extending the burnup to approximately 85 GWd/t and using the advanced fuel cladding tubes, though it slightly decreases with increasing initial hydrogen concentration.


Liquid film behavior and heat-transfer mechanism near the rewetting front in a single rod air-water system

和田 裕貴; Le, T. D.; 佐藤 聡; 柴本 泰照; 与能本 泰介

Journal of Nuclear Science and Technology, 57(1), p.100 - 113, 2020/01

The rewetting front propagation may occur when the fuel rod is cooled by the liquid film flow after it is dried out under accident conditions for BWR cores. Our previous study has revealed importance of precursory cooling, defined as a rapid cooling just before the rewetting, which has a significant effect on the propagation velocity. To understand the mechanism of the precursory cooling, we conducted heat transfer experiments using a single heater rod contained inside the transparent glass pipe to measure heat transfer behavior with simultaneous observation using a high-speed camera. The results showed characteristic effects of the wall temperature on the liquid film flow and liquid droplets formation at the rewetting front, i.e. sputtering. Even when the liquid film flows in rivulets under adiabatic condition, horizontally uniformed rewetting front was observed with increasing wall temperature due to enhanced flow resistance by sputtering. This sputtering effect was also confirmed from observations of the liquid film thickness, which increased with approaching the rewetting front. Heat transfer coefficients were predicted roughly well with a single-phase heat transfer correlation with entrance effects, suggesting the thinner thermal boundary layer downstream of the rewetting front may be one of the precursory cooling mechanisms.


Compton scattering of quasi-monochromatic $$gamma$$-ray beam

Omer, M.; 静間 俊行*; 羽島 良一*

Nuclear Instruments and Methods in Physics Research A, 951, p.162998_1 - 162998_6, 2020/01

Compton scattering of a single-energy $$gamma$$-ray results in a one-to-one relationship between the incident and scattered photon energies. This relationship is altered when the incident beam has a definite energy distribution because of the broadening occurring in the energy distribution upon Compton scattering. This broadening causes a change in the spectral density of the Compton-scattered spectra. To restore the spectral density, the energy distribution of the scattered radiation must be manifested as a function of the scattering kinematics. Here, we propose a simple analytic way to calculate the energy spread of the scattered photons in terms of the geometry of the scattering process and the energy spread of the incident photon beam. The predictions of the model agree with measurements of Compton scattering of quasi-monochromatic $$gamma$$-ray beams, carried out at the High Intensity $$gamma$$-ray Source (HI$$gamma$$S) facility, Duke University. As a benchmark of our method, we measured the intensity profile of energy-distributed $$gamma$$-ray beams by direct measurements as well as by Compton scattering. We found that only when the spectral density of the scattered radiation is restored, the measured intensity profile agrees with the actual profile of the incident beam. The proposed method can continuously measure the flux of an energy-distributed $$gamma$$-ray beams in the real time and on a bin-by-bin basis. Such online monitoring of $$gamma$$-ray beams is indispensable for in-beam measurements and applications. This work was supported by the subsidiary for promotion of strengthening nuclear security or the like of the Ministry of Education, Culture, Sports, Science, and Technology (MEXT), Japan.


Fine structure in the $$alpha$$ decay of $$^{223}$$U

Sun, M. D.*; Liu, Z.*; Huang, T. H.*; Zhang, W. Q.*; Andreyev, A. N.; Ding, B.*; Wang, J. G.*; Liu, X. Y.*; Lu, H. Y.*; Hou, D. S.*; et al.

Physics Letters B, 800, p.135096_1 - 135096_5, 2020/01

Fine structure in the $$alpha$$ decay of $$^{223}$$U was observed in the fusion-evaporation reaction $$^{187}$$Re($$^{40}$$Ar,p3n) by using fast digital pulse processing technique. Two $$alpha$$-decay branches of $$^{223}$$U feeding the ground state and 244 keV excited state of $$^{219}$$Th were identified by establishing the decay chain $$^{223}$$U$$rightarrow$$$$^{219}$$Th$$rightarrow$$$$^{215}$$Ra$$rightarrow$$$$^{211}$$Rn. The $$alpha$$-particle energy for the ground-state to ground-state transition of $$^{223}$$U was determined to be 8993(17) keV, 213 keV higher than the previous value, the half-life was updated to be 62$$^{+14}_{-10} mu$$s. Evolution of nuclear structure for $$N$$=131 even-$$Z$$ isotones from Po to U was discussed in the frameworks of nuclear mass and reduced $$alpha$$-decay width, a weakening octupole deformation in the ground state of $$^{223}$$U relative to its lighter isotones $$^{219}$$Ra and $$^{211}$$Th was suggested.



佐藤 義行; 青野 竜士; 原賀 智子; 石森 健一郎; 亀尾 裕

JAEA-Testing 2019-003, 20 Pages, 2019/12





安全・核セキュリティ統括部 安全・環境課

JAEA-Review 2019-016, 196 Pages, 2019/12




幌延深地層研究計画における人工バリア性能確認試験; 350m調査坑道における人工バリアの設置および坑道の埋め戻し

中山 雅; 大野 宏和

JAEA-Research 2019-007, 132 Pages, 2019/12




平成30年度研究開発・評価報告書; 評価課題「東京電力福島第一原子力発電所事故の対処に係る研究開発」のうち「廃止措置等に向けた研究開発」(中間評価)


JAEA-Evaluation 2019-009, 182 Pages, 2019/12




平成30年度研究開発・評価報告書; 評価課題「福島環境回復に関する技術等の研究開発」(中間評価)

福島研究開発部門 企画調整室

JAEA-Evaluation 2019-008, 129 Pages, 2019/12





尾上 博則; 竹内 竜史

JAEA-Data/Code 2019-010, 41 Pages, 2019/12




Positronium in room temperature ionic liquids

平出 哲也

AIP Conference Proceedings 2182, p.030007_1 - 030007_5, 2019/12



Biosurface properties and lead adsorption in a clone of ${it Sphagnum palustre}$ (Mosses); Towards a unified protocol of biomonitoring of airborne heavy metal pollution

Di Palma, A.; Gonz$'a$lez, A. G.*; Adamo, P.*; Giordano, S.*; Reski, R.*; Pokrovsky, O. S.*

Chemosphere, 236, p.124375_1 - 124375_9, 2019/12


In this work we used field- and laboratory-grown S. palustre moss treated by EDTA and devitalized by oven drying, to elaborate a consistent procedure of metal and proton adsorption on moss surfaces and a biomonitoring protocol using cloned moss. Devitalization and EDTA treatments did not produce any measurable difference in terms of H$$^{+}$$ and Pb$$^{2+}$$ adsorption capacities of moss surfaces. Therefore, in view of the use of S. palustre clone for biomonitoring purposes, we recommend devitalization as unique treatment to perform with the aim to preserve the biomaterial before and after its exposure in bags.



末岡 茂

フィッション・トラックニュースレター, (32), p.20 - 22, 2019/12


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