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Journal Articles

Hydrogen permeation through heat transfer pipes made of Hastelloy XR during the initial 950$$^{circ}$$C operation of the HTTR

Sakaba, Nariaki; Ohashi, Hirofumi; Takeda, Tetsuaki

Journal of Nuclear Materials, 353(1-2), p.42 - 51, 2006/07

 Times Cited Count:6 Percentile:43.58(Materials Science, Multidisciplinary)

The permeation of hydrogen isotopes through the Hastelloy XR high-temperature alloy adopted for the heat transfer pipes of the intermediate heat exchanger in the HTTR, is one of the concerns in the hydrogen production system, which will be connected to the HTTR in the near future. The hydrogen permeation between the primary and secondary coolant through the Hastelloy XR was evaluated using the actual hydrogen concentration observed during the initial 950$$^{circ}$$C operation of the HTTR. The hydrogen permeability of the Hastelloy XR was estimated conservatively high as follows. The activation energy E$$_{0}$$ and pre-exponential factor F$$_{0}$$ of the permeability of hydrogen were E$$_{0}$$ = 65.8 kJ/mol and F$$_{0}$$ = 7.8$$times$$10$$^{-9}$$m$$^{3}$$(STP)/(m$$ast$$s$$ast$$Pa$$^{0.5}$$), respectively, in the temperature range from 707K to 900K.

Journal Articles

Helium chemistry in high-temperature gas-cooled reactors; Chemistry control for avoiding Hastelloy XR corrosion in the HTTR-IS system

Sakaba, Nariaki; Hirayama, Yoshiaki*

Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 6 Pages, 2005/10

The high-temperature gas-cooled reactor (HTGR) is capable of producing a massive quantity of hydrogen with no carbon dioxide emission during its production by a thermo chemical IS (Iodine-Sulphur) process. The HTTR (High Temperature Engineering Test Reactor), which is the first high-temperature gas-cooled reactor in Japan, will be connected to some heat utilization system in the near future. The thermo chemical IS process is one of the progressive candidates. The metallic material of the heat transfer tube of the intermediate heat exchanger (IHX) and liner in the concentric hot gas duct in the HTTR-IS system, which allows usage in high-temperature conditions, is the nickel-based high-temperature alloy Hastelloy XR. Since the coolant helium contains small amounts of impurities, it is necessary to control the chemical composition in order to minimize corrosion of the Hastelloy XR. Major corrosion phenomena of the Hastelloy XR are carburization, decarburization, oxidation, and carbon deposition depending upon the particular gas composition and its temperature. The carburization and decarburization phenomena can be restricted by controlling the carbon activity and oxygen partial pressure. This paper describes the effect of each coolant impurity for the carburization and decarburization. Also a chemical composition limit was evaluated to avoid the Hastelloy XR corrosion.

Journal Articles

Evaluation of permeated hydrogen through heat transfer pipes of the intermediate heat exchanger during the initial 950$$^{circ}$$C operation of the HTTR

Sakaba, Nariaki; Matsuzawa, Takaharu*; Hirayama, Yoshiaki*; Nakagawa, Shigeaki; Nishihara, Tetsuo; Takeda, Tetsuaki

Proceedings of 2005 International Congress on Advances in Nuclear Power Plants (ICAPP '05) (CD-ROM), 8 Pages, 2005/05

The permeation of hydrogen isotopes through the Hastelloy XR high-temperature alloy adopted for the heat exchanger pipes of the intermediate heat exchanger in the HTTR (High Temperature Engineering Test Reactor) is one of the concerns in the hydrogen production system, which will be connected to the HTTR in the near future. An evaluation of the hydrogen permeation between the primary and secondary coolant through the Hastelloy XR was performed using the hydrogen concentration data observed during the initial 950$$^{circ}$$C operation of the HTTR. The hydrogen permeability of the Hastelloy XR was estimated conservatively high as follows. The activation energy E$$_{0}$$ and pre-exponential factor F$$_{0}$$ of the permeability of hydrogen were E$$_{0}$$ = 62 kJ/mol and F$$_{0}$$ = 3.6$$times$$10$$^{-5}$$ cm$$^{3}$$(NTP)/(cm s Pa$$^{0.5}$$), respectively, in the temperature range from 735K to 940K. The results implied that some oxidized film had been formed on the surface of the heat exchanger pipes of the intermediate heat exchanger.

Journal Articles

Structural design of high temperature metallic components

Tachibana, Yukio; Iyoku, Tatsuo

Nuclear Engineering and Design, 233(1-3), p.261 - 272, 2004/10

 Times Cited Count:22 Percentile:81.08(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Permeability of hydrogen and deuterium of Hastelloy XR

Takeda, Tetsuaki; Iwatsuki, Jin*; Inagaki, Yoshiyuki

Journal of Nuclear Materials, 326(1), p.47 - 58, 2004/03

 Times Cited Count:17 Percentile:74.24(Materials Science, Multidisciplinary)

Permeation of hydrogen isotope through a high-temperature alloy used as heat exchanger and steam reformer pipes is an important problem in the hydrogen production system connected to be a High-Temperature Engineering Test Reactor (HTTR). An experiment of hydrogen (H$$_{2}$$) and deuterium (D$$_{2}$$) permeation was performed to obtain permeability of H$$_{2}$$ and D$$_{2}$$ of Hastelloy XR, which is adopted as heat transfer pipe of an intermediate heat exchanger of the HTTR. Permeability of H$$_{2}$$ and D$$_{2}$$ of Hastelloy XR were obtained as follows. The activation energy E$$_{0}$$ and pre-exponential factor F$$_{0}$$ of the permeability of H$$_{2}$$ was E$$_{0}$$=67.2$$pm$$1.2 kJ/mol and F$$_{0}$$=(1.0$$pm$$0.2)$$times$$10$$^{-8}$$m$$^{3}$$(STP)/m$$^{-1}$$/s$$^{-1}$$/Pa$$^{-0.5}$$, respectively, in the pipe temperature ranging from 843K-1093K.

JAEA Reports

Study on hydrogen isotope permeation in the HTTR hydrogen production system, 2; Effectiveness of reducing the amount of permeated deuterium by oxidized film (Contract research)

Takeda, Tetsuaki; Iwatsuki, Jin*; Nishihara, Tetsuo

JAERI-Tech 2002-090, 30 Pages, 2002/11

JAERI-Tech-2002-090.pdf:5.44MB

Permeation of hydrogen isotope through a high-temperature alloy as used a heat transfer pipe of an intermediate heat exchanger and a steam reformer is an important problem in the hydrogen production system connected to be the high-temperature engineering test reactor (HTTR). In order to obtain detailed data for safety review and development of analytical codes, a test of permeation of hydrogen isotope was carried out as one of essential tests. The objective of this study is to obtain a permeability of hydrogen isotope through Hastelloy XR and other high temperature alloys and to evaluate quantitatively an effect of oxidized film on reducing the amount of permeated hydrogen through the pipe. From the results obtained in this experiment, it is supposed that the oxidized film produced on the surface of the heat transfer pipe during an early stage of the reactor operation will reduce the amount of tritium permeated from the primary circuit of the HTTR to the utilization system.

Journal Articles

Multiaxial creep behavior of nickel-base heat-resistant alloys Hastelloy XR and Ni-Cr-W superalloy at elevated temperatures

Kaji, Yoshiyuki; Tsuji, Hirokazu; Nishi, Hiroshi; Muto, Yasushi; Penkalla, H. J.*; Schubert, F.*

Journal of Nuclear Science and Technology, 39(8), p.923 - 928, 2002/08

 Times Cited Count:7 Percentile:45.84(Nuclear Science & Technology)

A series of uniaxial and multiaxial creep tests was carried out on Hastelloy XR and Ni-Cr-W superalloy, which were developed as the high temperature structural materials for nuclear application at the JAERI, in order to investigate multiaxial creep behavior of these materials and to verify the laws for the description of deformation under multiaxial loadings. Norton's creep law and von Mises' flow rule were applied to the prediction of multiaxial creep behavior of a tube under some significant loading conditions. In most cases the multiaxial creep behavior of these materials were successfully described with the constitutive equations based on the material parameters fitting uniaxial creep test results, though a few exceptional cases were observed. The present study has revealed that the method based on Norton's creep law and von Mises' flow rule are basically applicable for the description of the multiaxial creep behavior for Hastelloy XR and Ni-Cr-W superalloy as the conventional design method.

Journal Articles

Multiaxial creep behavior of nickel-base heat-resistant alloys Hastelloy XR and Ni-Cr-W superalloy at elevated temperatures

Tsuji, Hirokazu; Nishi, Hiroshi; Kaji, Yoshiyuki; Muto, Yasushi; Penkalla, H. J.*; Schubert, F.*

Proceedings of the 7th International Conference on Creep and Fatigue at Elevated Temperatures (CREEP7), p.101 - 106, 2001/06

A series of uniaxial and multiaxial creep tests was carried out on Hastelloy XR and Ni-Cr-W superalloy, which were developed as the high temperature structural materials for nuclear application at the JAERI, in order to investigate multiaxial creep behaviors of these materials. Norton's creep law and von Mises' flow rule were applied to the prediction of multiaxial creep behavior of a tube under some significant loading condition. In most cases the multiaxial creep behavior of these materials were successfully described with the constitutive equations based on the material parameter fitting uniaxial creep test results, though a few exceptional cases were observed. The present study has revealed that the method based on Norton's creep law and von Mises' flow rule are basically applicable for the description of the multiaxial creep behavior for Hastelloy XR and Ni-Cr-W superalloy as the conventional design method.

Journal Articles

Creep properties of base metal and welded joint of Hastelloy XR produced for high-temperature engineering test reactor in simulated primary coolant helium

Kurata, Yuji; *; *; Tsuji, Hirokazu; *; Shindo, Masami; Suzuki, Tomio

Journal of Nuclear Science and Technology, 36(12), p.1160 - 1166, 1999/00

 Times Cited Count:6 Percentile:46.57(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Creep damage in welded joints of a Ni-base heat-resistant alloy hastelloy XR

*; ; *; Tsuji, Hirokazu; *; Shindo, Masami

Mater. Sci. Eng., A, 234-236, p.1087 - 1090, 1997/00

no abstracts in English

Journal Articles

Feasibility study on the applicability of a diffusion-welded compact intermediate heat exchanger to next-generation high temperature gas-cooled reactor

Takeda, Takeshi; Kunitomi, Kazuhiko; *; *

Nucl. Eng. Des., 168, p.11 - 21, 1997/00

 Times Cited Count:39 Percentile:92.45(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Relation between fracture mode and M$$_{23}$$C$$_{6}$$/M$$_{6}$$C carbides of hastelloy XR creep-tested in helium environment

*; Kurata, Yuji; *; Yoshizu, Hiroshi*; ; *

Tetsu To Hagane, 83(5), p.43 - 48, 1997/00

no abstracts in English

JAEA Reports

Oxidation characteristics of oxide dispersion strengthened (ODS) alloy

; Watanabe, Katsutoshi; Shindo, Masami

JAERI-Research 95-088, 16 Pages, 1996/01

JAERI-Research-95-088.pdf:1.07MB

no abstracts in English

Journal Articles

Creep properties of 20% cold-worked Hastelloy XR

Kurata, Yuji; Nakajima, Hajime

Journal of Nuclear Materials, 228, p.176 - 183, 1996/00

 Times Cited Count:12 Percentile:71.65(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Temperature dependence of creep properties of cold-worked Hastelloy XR

Kurata, Yuji; Nakajima, Hajime

Journal of Nuclear Science and Technology, 32(6), p.539 - 546, 1995/06

 Times Cited Count:6 Percentile:55.97(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Seizure and wear characteristics of Hastelloy XR and titanium nitride coating in high temperature condition

Takeda, Takeshi; Kunitomi, Kazuhiko; *; *; *

The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering (ICONE),Vol. 1, 0, p.417 - 420, 1995/00

no abstracts in English

JAEA Reports

Effect of cold work on creep properties of Hastelloy XR

Kurata, Yuji; Nakajima, Hajime

JAERI-Research 94-004, 30 Pages, 1994/08

JAERI-Research-94-004.pdf:2.99MB

no abstracts in English

JAEA Reports

Creep properties of 20% cold worked Hastelloy XR

Kurata, Yuji; Nakajima, Hajime

JAERI-M 94-022, 28 Pages, 1994/02

JAERI-M-94-022.pdf:0.9MB

no abstracts in English

Journal Articles

Effect of cold work on creep properties of Ni-22Cr-18Fe-9Mo alloy

Kurata, Yuji; Hamada, Shozo; Nakajima, Hajime

Proc. of 10th Int. Conf. on Strength of Materials; ICSMA 10, 0, p.677 - 680, 1994/00

no abstracts in English

Journal Articles

Inspection performance of eddy current probe for in-service inspection of HTTR intermediate heat exchanger tubes

Inagaki, Yoshiyuki; ; *; *

Nihon Genshiryoku Gakkai-Shi, 35(3), p.227 - 236, 1993/03

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

31 (Records 1-20 displayed on this page)