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Journal Articles

Measurement of thermal property for tungsten-stainless steel alloy and high purity tungsten

Kawai, Masayoshi*; Li, J.*; Watanabe, Ryuzo*; Kurishita, Hiroaki*; Kikuchi, Kenji; Igarashi, Tadashi*; Kato, Masahiro*

Dai-23-Kai Nippon Netsu Bussei Shimpojiumu Koen Rombunshu, p.313 - 315, 2002/11

The objective of the present study is to develop the stainless-steel-bonded tungsten alloys by powder metallurgy processes. Commercially available tungsten powders and stainless steel (SUS304L) powder were used as the raw materials and mixed by ball milling at the ratios of 97mass% W -3% SUS and 93mass% W -7mass% SUS. Powder compacts were formed by die pressing and cold isostatic pressing (CIP), then sintered mainly in vacuum at the temperatures above the melting point of the stainless steel phase. Some samples were fabricated by glass-encapsulated hot isostatic pressing (HIPing) at lower temperatures. The microstructural observation was made by scanning electron microscopy (SEM). The thermal properties of the produced alloy and various tungsten materials supplied from Allied Material Corp. was measured with the laser-frash method. It was found that stable liquid-phase-sintered microstructures were not easily formed in the tungsten-stainless steel system. The electron probe microanalysis (EPMA) revealed that tungsten was considerably dissolved in the stainless steel phase during sintering. Therefore, thermal conductivity of the W/7 mass% SUS alloy was 22.8-53.5 W/m/K that was very lower than theoretical value calculated from those of pure tungsten and stainless steel. Its temperature dependence is resembled to that of stainless steel, i.e., thermal conductivity increased with the specimen temperature as like stainless steel. The diffusivity of pure tungsten is compared with those of tungsten alloys.

JAEA Reports

Simulation tests for thermal characteristics of JCO precipitation vessel using a mock-up device

Watanabe, Shoichi; Miyoshi, Yoshinori; Yamane, Yuichi

JAERI-Tech 2002-043, 93 Pages, 2002/03

JAERI-Tech-2002-043.pdf:6.74MB

no abstracts in English

Journal Articles

Recent progress and future R&D for high-chromium iron-base and chromium-base alloys

Hishinuma, Akimichi; Takaki, Seiichi*; Abiko, Kenji*

Physica Status Solidi (A), 189(1), p.69 - 78, 2002/01

 Times Cited Count:12 Percentile:44.81

no abstracts in English

Journal Articles

Thermal properties of pellet

Nakamura, Jinichi

Saishin Kaku Nenryo Kogaku; Kodoka No Genjo To Tembo, p.93 - 98, 2001/06

no abstracts in English

JAEA Reports

Measurements of thermal properties of buffer materials; Measurement of physical properties of buffer materials and improvement of measuring method

*

JNC-TJ8400 2000-017, 74 Pages, 2000/02

JNC-TJ8400-2000-017.pdf:1.71MB

The report concerns the improvement of the method measuring thermal conductivity of buffer materials using a thermistor probe and the measurement of thermal conductivity of compacted bentonites and mixtures of bentonite and silica sand using the proposed method measuring thermophysical properties. The method measuring thermal conductivity is improved in accuracy and the apparatus is improved so as to measure easily with more short time. The calculated values of the conventional correlations predicting thermal conductivity of bentonite and mixture were compared with the exising and present data of thermal conductivity of bentonites and mixtures. The correlation proposed by Sakashita and Kumada can predict the best fitted values with the data of the bentonites and Fricke and Bruggeman correlations are fitted with the data for the mixtures with practical accuracy.

JAEA Reports

Evaluation of Coupled Thermo-Hydro-Mechanical Phenomena in the Near Field for Geological Diaposal of High-Level Radioactive waste

Chijimatsu, Masakazu*; Fujita, Tomoo; Sugita, Yutaka; Taniguchi, Wataru

JNC-TN8400 2000-008, 339 Pages, 2000/01

JNC-TN8400-2000-008.pdf:15.57MB

Geological disposal of high-level radioactive waste (HLW) in Japan is based on a multibarrier system composed of engineered and natural barriers. The engineered barriers are composed of vitrified waste confined within a canister, overpack and buffer material. Highly compacted bentonite clay is considered one of the most promising candidate buffer material mainly because of its low hydraunc conductivity and high adsorption capacity of radionuclides. In a repository for HLW, complex thermal, hydraulic and mechanical (T-H-M) phenomena will take place, involving the interactive processes between radioactive decay heat from the vitrified waste, infiltration of ground water and stress generation due to the earth pressure, the thermal loading and the swelling pressure of the buffer material. In order to evaluate the performance of the buffer material, the coupled T-H-M behaviors within the compacted bentonite have to be modelled. Before establishing a fully coupled T-H-M model, the mechanism of each single Phenomenon or partially coupled phenomena should be identified. Furthermore, in order to evaluate the coupled T-H-M phenomena, the analysis model was developed physically and numerically and the adequacy and the applicability was tested though the engineered scale laboratory test and in-situ test. In this report, the investigative results for the development of coupled T-H-M model were described. This report consists of eight chapters. In Chapter l, the necessity of coupled T-H-M model in the geological disposal project of the high-level radioactive waste was described. In Chapter 2, the laboratory test results of the rock sample and the buffer material for the coupled T-H-M analysis were shown. nle rock samples were obtained from the in-situ experimental site at Kamaishi mine. As the buffer material, bentonite clay (Kunigel V1 and Kunigel OT-9607) and bentonite-sand mixture were used. In Chapter 3, in-situ tests to obtain the rock property were shown. As ...

JAEA Reports

Data collection by literature survey on rock physical properties in Japan (II)

Sato, Toshinori; Taniguchi, Wataru; Fujita, Tomoo; Hasegawa, Hiroshi

JNC-TN7400 99-011, 36 Pages, 1999/12

JNC-TN7400-99-011.pdf:1.55MB

In order to understand the general thermal and mechanical properties of rock masses and initial stress of rock at depth, data were compiled from the published literature in Japan and collected from investigations carried out at Kamaishi mine and Tono mine. Statistical examinations derived the ranges, means and medians of the mechanical properties for the different rock types. It was confirmed that the correlations between the mechanical properties were in agreement with correlations determined previously in other similar surveys. The unconfined compressive strength of Neogene sedimentary rocks showed a tendency to increase with increasing depth ($$geq$$ 500 m). An examination of the measured initial stress data collected through literature surveys showed that the vertical stress can be approximated by the extent of gravitational loading at a particular point. There is an approximately linear relationship between the average stress in a horizontal plane and the depth. The lateral pressure coefficient tends to have a high value and large range at shallow depths, but tends towards $$<$$ 1 with increasing depth.

JAEA Reports

SIMMER-III Analytic Equation-of-State Model

Morita, Koji; Tobita, Yoshiharu; kondo, Satoru; E.A.Fischer*

JNC-TN9400 2000-005, 57 Pages, 1999/05

JNC-TN9400-2000-005.pdf:2.92MB

An improved analytic equation-of-state (EOS) model using flexible thermodynamic functions is developed for a reactor safety analysis code, SIMMER-III. The present EOS model is designed to have adequate accuracy in describing thermodynamic properties of reactor-core materials over wide temperature and pressure ranges and to consistently satisfy basic thermodynamic relationships without deterioration of the computing efficiency. The fluid-dynamic algorithm for pressure iteration consistently coupled with the EOS model is also described in the present report. The EOS data of the basic core materials, uranium dioxide, mixed-oxide fuel, stainless steel, and sodium, are developed up to the critical point by compiling the most up-to-date and reliable sources using basic thermodynamic relationships. The thermodynamic consistency and accuracy of the evaluated EOS data are also discussed by comparison with the available sources.

JAEA Reports

SIMMER-III Analytic Thermophysical Property Model

Morita, Koji; Tobita, Yoshiharu; kondo, Satoru; E.A.Fischer*

JNC-TN9400 2000-004, 38 Pages, 1999/05

JNC-TN9400-2000-004.pdf:1.11MB

An analytic thermophysical property model using general function forms is developed for a reactor safety analysis code, SIMMER-III. The function forms arc designed to represent correct behavior of properties of reactor-core materials over wide temperature ranges, especially for the thermal conductivity and the viscosity near the critical point. The most up-to-date and reliable sources for uranium dioxide, mixed-oxide fuel, stainless stee1, and sodium available at present are used to determine parameters in the proposed functions. This model is also designed to be consistent with a SIMMER-III model on thermodynamic properties and equations of state for reactor-corc materials.

JAEA Reports

Safety analysis of JMTR core with 6-MEU fuel elements and 16-LEU fuel elements

Tabata, Toshio; Komukai, Bunsaku; Nagao, Yoshiharu; Shimakawa, Satoshi; Koike, Sumio; Takeda, Takashi; Fujiki, Kazuo

JAERI-Tech 99-021, 68 Pages, 1999/03

JAERI-Tech-99-021.pdf:2.6MB

no abstracts in English

JAEA Reports

Radiation-induced crosslinking of short fiber-filled polytetrafluoroethylene (PTFE)

*; Udagawa, Akira; Morita, Yosuke

JAERI-Tech 99-012, 15 Pages, 1999/02

JAERI-Tech-99-012.pdf:1.09MB

no abstracts in English

JAEA Reports

None

*

PNC-TJ1600 98-003, 28 Pages, 1998/02

PNC-TJ1600-98-003.pdf:0.68MB

None

Journal Articles

Beryllium neutron irradiation study in the Japan Materials Testing Reactor

Ishitsuka, Etsuo; Kawamura, Hiroshi

Fusion Engineering and Design, 41, p.195 - 200, 1998/00

 Times Cited Count:2 Percentile:74.35(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Report on international meeting 「International Seminar on Thermal Performance of (high burnup) LWR Fuel」

Nakamura, Jinichi

Kaku Nenryo, (29), P. 15, 1998/00

no abstracts in English

JAEA Reports

None

*; Fukazawa, E.*; *; Kubota, Shigeru*

PNC-TJ1449 97-004, 901 Pages, 1997/03

PNC-TJ1449-97-004.pdf:30.83MB

None

JAEA Reports

Design study on large-scale mercury loop for engineering test of target of high-intensity proton accelerator

Hino, Ryutaro; Haga, Katsuhiro; ; ; *; Kaminaga, Masanori; Sudo, Yukio; *

JAERI-Tech 97-009, 50 Pages, 1997/03

JAERI-Tech-97-009.pdf:3.43MB

no abstracts in English

JAEA Reports

None

*

PNC-TJ1600 97-004, 40 Pages, 1997/02

PNC-TJ1600-97-004.pdf:0.76MB

None

Journal Articles

Characterization of self-powered neutron detector at high temperature under neutron irradiation

Nakamichi, Masaru; *; Kawamura, Hiroshi; Sagawa, Hisashi; Nakazawa, Masaharu*

Fusion Technology 1996, 0, p.1591 - 1594, 1997/00

no abstracts in English

Journal Articles

Thermal properties of neutron irradiated beryllium

Ishitsuka, Etsuo; Kawamura, Hiroshi; Terai, Takayuki*; Tanaka, Satoru*

Proc. of 5th Int. Workshop on Ceramic Breeder Blanket Interaction, 0, p.215 - 220, 1996/00

no abstracts in English

JAEA Reports

None

PNC-TJ1678 95-006, 181 Pages, 1994/11

PNC-TJ1678-95-006.pdf:5.25MB

None

32 (Records 1-20 displayed on this page)