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ICONE23-1687 INCLINED DROP TEST OF A CC-440 PACKAGING SYSTEM

Rosa Lo Frano、Antonio Sanfiorenzo、Giovanni Pugliese 等 4 位作者2015-01-01The Proceedings of the International Conference on Nuclear Engineering (ICONE)

To safely transport radioactive materials it is required that the packaging system must be able to guarantee their containment and confinement (via its integrity assurance) avoiding any additional dose exposure (respect of ALARA principle). The engineering system has thus to be designed to ensure safety features by co…

Material Properties and ProcessingGraphite, nuclear technology, radiation studiesNuclear and radioactivity studies

29pm1-F-3 Self-healing of crack on stretching wire

Tomoya Koshi、Eiji Iwase2015-01-01The Proceedings of the Symposium on Micro-Nano Science and Technology

This paper reports self-healing of a crack on a stretching metal wire using electric field trapping of metal nanoparticles. The electric field trapping is a phenomenon where the nanoparticles are trapped in a crack on the wire selectively by the electric field, when a voltage is applied to the wire covered with the na…

Surface Modification and SuperhydrophobicityAdvanced Sensor and Energy Harvesting MaterialsNanomaterials and Printing Technologies

OS1422-385 Slip deformation behavior of single crystals with Perovskite structure at room temperature

Atsutomo Nakamura、Kensuke Yasufuku、Yuuho FURUSHIMA 等 5 位作者2015-01-01The Proceedings of the Materials and Mechanics Conference

It is well known that ceramic materials generally exhibit brittle nature at low temperatures. This is because the translation vector of crystal structure is large and accordingly the Peierls stress of possible dislocations is large. It is noted that perovskite crystals such as strontium titanate often exhibit ductile…

Ferroelectric and Piezoelectric MaterialsAdvanced ceramic materials synthesisIntermetallics and Advanced Alloy Properties

ICONE23-1007 VALIDATION OF RELAP5/MOD3.2 CODE FOR SIMULATING NUCLEATE POOL BOILING HEAT TRANSFER OUTSIDE VERTICAL TUBE BUNDLE

Wenjing Lei、Xiaxin Cao、Ya Li 等 6 位作者2015-01-01The Proceedings of the International Conference on Nuclear Engineering (ICONE)

In the new generation of nuclear reactors design, a series of passive safety systems are adopted to provide significant improvements in plant simplification, safety and reliability. However, when applying the RELAP5 code in predicting the passive residual heat removal system (PRHRS), the capability of RELAP5 code need…

Nuclear reactor physics and engineeringNuclear Materials and PropertiesNuclear Engineering Thermal-Hydraulics

ICOPE-15-1118 Evaluation of material degradation in sea-water for development of ocean current power generation system

Shoichi Miyashiro、Atsushi Tanaka、L. Yan 等 8 位作者2015-01-01The Proceedings of the International Conference on Power Engineering (ICOPE)

Ocean current power generation is expected to be renewable and stable energy source. Floating type ocean current power generation system is under development by joint research consortium comprised of TOSHIBA, IHI, the University of Tokyo and Mitsui Global Strategic Studies Institute. This system will be mainly operate…

Industrial Engineering and TechnologiesMaterial Properties and ApplicationsEngineering Diagnostics and Reliability

Программная реализация метода конечных элементов для уравнения диффузии нейтронов

Аввакумов Александр Владимирович、Васильев Александр Олегович、Захаров Петр Егорович2015-01-01CyberLeninK (CyberLeninka)

The most of engineering codes, used in nuclear reactor calculations, are based on diffusion approximation of the neutron transport equation. The finite-difference method is widely used to solve the diffusion equation. Acceptable accuracy of the results reached only by using fine mesh or complementary approaches, such…

Nuclear reactor physics and engineeringNuclear Materials and PropertiesNuclear and radioactivity studies

J1630305 Study on evaluation of contact stimulus by diaper considering pressure distribution

Mami TANAKA、Yuuki Taniguchi、Takeshi OKUYAMA2015-01-01The Proceedings of Mechanical Engineering Congress Japan

Recently, most of infants wear diapers in their daily life. Due to wearing a diaper, contact stimuli on skin causes dermatitis. The contact stimulus is measured by sensory evaluation. However, it is difficult to carry out sensory evaluation on infants. Therefore, a sensory system which can objectively evaluate the con…

Interactive and Immersive DisplaysTextile materials and evaluationsErgonomics and Musculoskeletal Disorders

GS0706-432 The Fabrication of High Density Single Crystal Al Nanowires by Stress Migration

Takamasa Suzuki、Yuhki TOKU、Yasuyuki MORITA 等 4 位作者2015-01-01The Proceedings of the Materials and Mechanics Conference

Nanowires have been expected to be utilized in various applications. Recently, many researchers have reported about single crystal or polycrystalline nanowires where the single crystal nanowires are shown to have a higher conductivity compared to the polycrystalline ones. In our previous study, we investigated the fab…

Anodic Oxide Films and Nanostructures

PS0013-240 Stress Effect on Ionic Conductivity on Oxygen Permeation Membrane

Naoki Otsuka、Wakako Araki、Yoshio Arai2015-01-01The Proceedings of the Materials and Mechanics Conference

La_<0.6>Sr_<0.4>Co_<0.8>Fe_<0.2>O_<3-δ>(LSCF) is expected to be applied as an oxygen separation membrane and cathode for solid oxide fuel cell (SOFCs) because of its oxygen ion conductivity. In particular, the oxygen ion conductivity of LSCF is an important characteristic that determines the performance of the device.…

Advancements in Solid Oxide Fuel CellsFuel Cells and Related Materials

ICONE23-2024 DEVELOPMENT OF "INTERMEDIATE HEAT EXCHANGE" SIMULATOR OF THE DMS FOR CO-GENERATION

Tomohiko Ikegawa、Kazuaki Kito、Koji Nishida2015-01-01The Proceedings of the International Conference on Nuclear Engineering (ICONE)

Hitachi-GE Nuclear Energy Ltd. (Hitachi-GE) has developed a conceptual design for the Double MS: modular simplified & medium small reactor (DMS) under the sponsorship of The Japan Atomic Power Company. The DMS is one of the small-to-medium sized reactors (SMRs) of boiling water reactor (BWR) type, which has been predi…

Nuclear reactor physics and engineeringNuclear Materials and PropertiesNuclear and radioactivity studies

0106 Power Consumption of Large Paddle Impeller for Shear Thinning Fluid

Haruki Furukawa、Norihisa Nakamura、Yoshihito Kato2015-01-01Ryuutai Kougaku Bumon Kouenkai kouen rombunshuu/Ryutai Kogaku Bumon Koenkai koen ronbunshu

Power consumption of large paddle impellers was measured for shear thinning fluids. The large paddle impellers are MAXBLEND, FULLZONE, Super Mix MR203 and Super Mix MR205. The test fluids were 3.5wt%, 4.0wt%, 4.5wt% carboxymethylcellulose(CMC) solutions. The shear stress of CMC solutions was correlated with the power…

Metallurgy and Material FormingTextile materials and evaluationsMaterial Properties and Processing

G0600605 The Effective Thermal Conductivity of Metal Hydride Sheet and its Application in the Metal Hydride Heat Pump System

Yongjian Yang、Kuan-Ting Lin、Sangchul Bae 等 4 位作者2015-01-01The Proceedings of Mechanical Engineering Congress Japan

Metal hydride heat pump (MHHP) shows low cooling performance due to the low effective thermal conductivity of metal hydrides (MH) particle bed. In this paper, aiming at improving the heat transfer of MH particle bed as well as enhancing the operating characteristic of the MHHP system, the metal hydride sheet (MH sheet…

Hydrogen Storage and MaterialsHeat Transfer and OptimizationThermodynamic and Structural Properties of Metals and Alloys

ICONE23-1476 PHENOMENOLOGICAL ANALYSIS OF MELT PROGRESSION IN LWRS : PROPOSAL OF AN IN-VESSEL CORIUM PROGRESSION SCENARIO IN THE UNIT 1 OF FUKUSHIMA DAI-ICHI NUCLEAR POWER PLANT

F. Payot、Seiler Jean-Marie2015-01-01The Proceedings of the International Conference on Nuclear Engineering (ICONE)

In the field of severe accident, the description of corium progression events is mainly carried out by using integral calculation codes. However, these tools are usually based on bounding assumptions because of high complexity of phenomena. The limitations associated with bounding situations ([Seiler et al., 2014] e.g…

Fusion materials and technologiesNuclear reactor physics and engineeringNuclear Materials and Properties

Size-Controllable Synthesis of Inorganic Nanophosphors

Satoru Takeshita2015-01-01Journal of the Japan Society of Colour Material

可視光に対して吸収も散乱ももたないナノ粒子蛍光体は,インビジブル(目に見えない)であることを活かしてさまざまな応用が期待されている。光散乱強度と比表面積の観点から,インビジブル蛍光体には粒子サイズが10 ~50 nm程度でよく制御され,適切なマトリクス中でよく分散するナノ粒子が求められる。このようなナノ粒子を合成するためには,ソルボサーマル法・ポリオール法などの焼成を経ない低温液相プロセスが有効である。本解説では,セラミックスナノ粒子の液相合成において粒子サイズを決める因子を概観し,ナノ粒子蛍光体のサイズ制御合成の実例を紹介する。

Luminescence Properties of Advanced MaterialsQuantum Dots Synthesis And PropertiesInorganic Chemistry and Materials

ICONE23-2083 FULL SCALE BWR CONTAINMENT LOCA RESPONSE TEST AT THE INKA TEST FACILITY

Thomas Wagner、Stephan Leyer2015-01-01The Proceedings of the International Conference on Nuclear Engineering (ICONE)

KERENA is an innovative boiling water reactor concept with passive safety systems (Generation III+) of AREVA. The reactor is an evolutionary design of operating BWRs (Generation II). In order to verify the functionality and performance of the KERENA safety concept required for the transient and accident management, th…

Nuclear reactor physics and engineeringNuclear Materials and PropertiesNuclear Engineering Thermal-Hydraulics

ICONE23-1473 Improvement of transient analysis method of a sodium-cooled fast reactor with FAIDUS fuel sub-assemblies

Kazuya Ohgama、K Kawashima、Shigeo Ohki2015-01-01The Proceedings of the International Conference on Nuclear Engineering (ICONE)

In order to evaluate transient behavior of Japan sodium-cooled fast reactor (JSFR) with fuel sub-assemblies with the innerduct structure (FAIDUS) precisely, a new model for a plant dynamics code HIPRAC was developed. In this new model, inner core and outer core channels can be divided into three channels, respectively…

Nuclear reactor physics and engineeringNuclear Materials and PropertiesNuclear Engineering Thermal-Hydraulics

Preparation of Cr-Mg-N-O Ceramics by Spark Plasma Sintering

Hiroki Asami、Kohei Matsumoto、Koji Takazawa 等 5 位作者2015-01-01Journal of the Japan Institute of Metals and Materials

Cr1−x-Mgx-N-O powders, with Mg content in metallic elements (x=Mg/Cr+Mg) ranging from 0 to 0.5, were synthesized from CrN and MgO powders using mechanical alloying under nitrogen atmosphere. Densification of these original powders is carried out by the spark plasma sintering is performed under a 70 MPa pressure and at…

Advanced ceramic materials synthesisMetal and Thin Film MechanicsAdvanced materials and composites

313 Damage Behavior of Carbon Fiber Reinforced Plastics blended with Polycyanate Esters under Thermal Cyclic Environment

Tomoaki Shimpo、Satoshi KOBAYASHI、Ken Goto 等 4 位作者2015-01-01Kikai Zairyou, Zairyou Kakou Gijutsu Kouenkai kouen rombunshuu/Kikai Zairyo, Zairyo Kako Gijutsu Koenkai koen ronbunshu

In the present study, long term durability of the candidate material for the next radio astronomy satellite under space environment were investigated. The materials were high modulus PAN based carbon fiber reinforced polycyanate ester and epoxy. In order to simulate the space environment, thermal cycle tests between -…

Synthesis and properties of polymersSilicone and Siloxane ChemistryMaterial Properties and Applications

ICONE23-1076 3D SIMULATION TECHNOLOGIES FOR REACTOR DECOMMISSIONING

Yongling Zhang、Yifei Hu、Meng Liu 等 6 位作者2015-01-01The Proceedings of the International Conference on Nuclear Engineering (ICONE)

A prototype 3D simulation system for reactor decommissioning based on the software of DELMIA, and VIRTOOLS is built. This system is composed of the database, real simulating scene, decommissioning process simulating, decommissioning data analyzing, project management, evaluation and expert assistant decision-making an…

Graphite, nuclear technology, radiation studies

ЭЛЕКТРОДНЫЕ ПОТЕНЦИАЛЫ УРАНА В РАСПЛАВЕ ЭВТЕКТИЧЕСКОЙ СМЕСИ LICL-KCL-CSCL

Б Д Васин、Evgeny N. Vladykin、Vladimir A. Volkovich 等 4 位作者2015-01-01Расплавы

Измерены электродные потенциалы урана в расплаве эвтектической смеси хлоридов лития, калия и цезия в интервале 573-1073 K. Рассчитаны условные стандартные потенциалы E U*(III)/U и основные термодинамические характеристики трихлорида урана в расплаве LiCl-KCl-CsCl, измерены электронные спектры поглощения ионов UCl 3- 6

Nuclear Materials and PropertiesMolten salt chemistry and electrochemical processesThermodynamic and Structural Properties of Metals and Alloys