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Journal Articles

J-PARC transmutation experimental facility programme

Sasa, Toshinobu; Takei, Hayanori; Saito, Shigeru; Obayashi, Hironari; Nishihara, Kenji; Sugawara, Takanori; Iwamoto, Hiroki; Yamaguchi, Kazushi; Tsujimoto, Kazufumi; Oigawa, Hiroyuki

NEA/CSNI/R(2015)2 (Internet), p.85 - 91, 2015/06

Nuclear transmutation got much interested as an effective option of nuclear waste management. Japan Atomic Energy Agency (JAEA) proposes the transmutation of minor actinides (MA) by accelerator-driven system (ADS) using lead-bismuth alloy (Pb-Bi). To obtain the data for ADS design, JAEA plans to build a Transmutation Experimental Facility (TEF) in the J-PARC project. TEF consists of two buildings, an ADS target test facility (TEF-T) with 400MeV-250kW Pb-Bi target, and a Transmutation Physics Experimental Facility (TEF-P), which set up a fast critical assembly driven by low power proton beam with MA fuel. In TEF-T, irradiation test for materials, and engineering tests for Pb-Bi target operation will be performed. Various research plans such as nuclear data measurements have been proposed and layout of the experimental hall are underway. In the presentation, roadmap to establish the ADS transmutor and latest design activities for TEF construction will be summarized.

Journal Articles

Comparison of the corrosion behavior of austenitic and ferritic/martensitic steels exposed to static liquid Pb-Bi at 450 and 550 $$^{circ}$$C

Kurata, Yuji; Futakawa, Masatoshi; Saito, Shigeru

Journal of Nuclear Materials, 343(1-3), p.333 - 340, 2005/08

 Times Cited Count:56 Percentile:96.16(Materials Science, Multidisciplinary)

In order to study effects of temperature and alloying elements on corrosion behavior in liquid Pb-Bi which will be used for an accelerator driven system (ADS), corrosion tests of various steels were conducted under static liquid Pb-Bi condition. The tests were performed in oxygen-saturated liquid Pb-Bi at 450$$^{circ}$$C and 550$$^{circ}$$C for 3000h. Oxide films were formed during corrosion at 450$$^{circ}$$C and 550$$^{circ}$$C. Corrosion depth of steels decreased at 450$$^{circ}$$C with increasing Cr content of steels. Austenitic stainless steels containing Ni didn't exhibit appreciable dissolution of Ni and Cr at 450$$^{circ}$$C. The thick ferrite layer produced by dissolution of Ni and Cr was found in JPCA and type 316ss at 550$$^{circ}$$C. For this reason the corrosion depth of austenitic stainless steels, JPCA and type 316ss became large. A Si-added austenitic stainless steel showed good corrosion resistance at 550$$^{circ}$$C because a protective oxide film formed on the steel prevented dissolution of Ni and Cr into liquid Pb-Bi.

JAEA Reports

Corrosion behavior of austenitic and ferritic/martensitic steels in oxygen-saturated liquid Pb-Bi eutectic at 450$$^{circ}$$C and 550$$^{circ}$$C

Kurata, Yuji; Futakawa, Masatoshi; Saito, Shigeru

JAERI-Research 2005-002, 37 Pages, 2005/02

JAERI-Research-2005-002.pdf:20.04MB

Static corrosion tests of various austenitic and ferritic/martensitic steels were conducted in oxygen-saturated liquid Pb-Bi at 450$$^{circ}$$C and 550$$^{circ}$$C for 3000h to study the effects of temperature and alloying elements on corrosion behavior. Oxidation, grain boundary corrosion, dissolution and penetration were observed. The corrosion depth decreases at 450$$^{circ}$$C with increasing Cr content in steels regardless of ferritic/martensitic or austenitic steels. Appreciable dissolution of Ni and Cr does not occur in the three austenitic steels at 450$$^{circ}$$C. The corrosion depth of ferritic/martensitic steels also decreases at 550$$^{circ}$$C with increasing Cr content whereas the corrosion depth of austenitic steels, JPCA and 316ss becomes larger due to ferritization caused by dissolution of Ni at 550$$^{circ}$$C than that of ferritic/martensitic steels. An austenitic stainless steel containing about 5%Si exhibits fine corrosion resistance at 550$$^{circ}$$C because the protective Si oxide film is formed and prevents dissolution of Ni and Cr.

Journal Articles

Corrosion behavior of Al-surface-treated steels in liquid Pb-Bi in a pot

Kurata, Yuji; Futakawa, Masatoshi; Saito, Shigeru

Journal of Nuclear Materials, 335(3), p.501 - 507, 2004/12

 Times Cited Count:26 Percentile:83.83(Materials Science, Multidisciplinary)

Corrosion tests were performed in oxygen-saturated liquid Pb-Bi at 450$$^{circ}$$C and 550$$^{circ}$$C in a pot for 3000h for Al-surface-treated steels containing various levels of Cr contents. The Al surface treatments were achieved using a gas diffusion method and a melt dipping method. Al$$_{2}$$O$$_{3}$$, FeAl$$_{2}$$ and AlCr$$_{2}$$ produced by the gas diffusion method exhibited corrosion resistance to liquid Pb-Bi, while the surface layer produced by the melt dipping method suffered a severe corrosion attack. Fe$$_{4}$$Al$$_{13}$$ and Fe$$_{2}$$Al$$_{5}$$ produced by the melt dipping method disappeared during the corrosion test at 550$$^{circ}$$C and only FeAl remained.

Journal Articles

Excellent corrosion resistance of 18Cr-20Ni-5Si steel in liquid Pb-Bi

Kurata, Yuji; Futakawa, Masatoshi

Journal of Nuclear Materials, 325(2-3), p.217 - 222, 2004/09

 Times Cited Count:30 Percentile:87.54(Materials Science, Multidisciplinary)

The corrosion properties of three austenitic steels with different Si contents were studied under oxygen-saturated liquid Pb-Bi condition for 3000h. The three austenitic steels did not exhibit appreciable dissolution of Ni and Cr at 450$$^{circ}$$C. At 550$$^{circ}$$C, the thick ferrite layer produced by dissolution of Ni and Cr was found in JPCA and 316ss with low Si contents while the protective oxide film composed of Si and O was formed on 18Cr-20Ni-5Si steel and prevented dissolution of Ni and Cr. It was found that the Si added austenitic steel exhibited excellent corrosion resistance in liquid Pb-Bi.

Journal Articles

Lead-bismuth eutectic compatibility with materials in the concept of spallation target for ADS

Kikuchi, Kenji; Saito, Shigeru; Kurata, Yuji; Futakawa, Masatoshi; Sasa, Toshinobu; Oigawa, Hiroyuki; Wakai, Eiichi; Umeno, Makoto*; Mizubayashi, Hiroshi*; Miura, Kuniaki*

JSME International Journal, Series B, 47(2), p.332 - 339, 2004/05

Lead bismuth eutectic (LBE) is favored by spallation neutron sources and coolant in the sub-critical reactor at the accelerator driven nuclear transmutation system (ADS). Technical issues of ADS are material technology of how to compromise with flowing lead bismuth, high-energy proton accelerator technology and a sub-critical reactor system technology. This paper describes LBE technology developed at JAERI. First a scenario in order to realize the ADS is shown. The concept of spallation target test facility is introduced with a target design of thermo-fluid dynamics. Base data of flow rate and temperature of Pb-Bi during LBE circulation are described. The results of LBE loop operation under the flowing conditions of target design concept are reported. The stagnant corrosion tests were done to know the controlling parameters among the various steels. The tube-type oxygen sensor with having the solid electrolyte was studied. Cleaning techniques were developed to remove LBE from materials.

Journal Articles

Research and development on lead-bismuth technology for accelerator-driven transmutation system at JAERI

Kurata, Yuji; Kikuchi, Kenji; Saito, Shigeru; Kamata, Kinya*; Kitano, Teruaki*; Oigawa, Hiroyuki

Proceedings of 4th International Workshop on the Utilisation and Reliability of High Power Proton Accelerators, p.267 - 277, 2004/05

R&D on lead-bismuth technology have been conducted for accelerator driven system. From the test results of 316SS using JLBL-1 for 3000h without active oxygen control, mass transfer from high temperature to low temperature parts was observed. It was found that deposition of Pb/Bi and Fe-Cr grains in the annular channel of the electro-magnetic pump caused plugging and decrease in flow rate. The modification of the loop system brought about a good effect on operation. Significant erosion/corrosion was not observed in the experiment using MES loop for 1000h under 10$$^{-5}$$wt.% oxygen condition. The results of static corrosion tests showed the following: corrosion depth decreased at 450$$^{circ}$$C with increasing Cr content in steels while corrosion depth of JPCA and 316SS became larger due to ferritization caused by dissolution of Ni and Cr at 550$$^{circ}$$C. Si-added steel exhibited good corrosion resistance at 550$$^{circ}$$C.

Journal Articles

Main results of static and dynamic corrosion tests in oxygen-saturated liquid lead-bismuth

Kurata, Yuji; Kikuchi, Kenji; Saito, Shigeru; Futakawa, Masatoshi; Sasa, Toshinobu

FZKA-6876, p.190 - 198, 2003/12

A report at MEGAPIE(Megawatt Pilot Experiment) Technical R & D Meeting is collected into an FZK report. According to the static corrosion tests, Al surface-treated layer produced by the gas diffusion method exhabited corrosion resistance to liquid Pb-Bi, while Al surface-treated layer produced by the melt dipping method suffered a severe corrosion attack. Furtheremore, it was found that a thick ferrite layer was formed in the surface of austenitic stainless steel at 550$$^{circ}$$C. Dissolution at high temperature parts, precipitation of Fe-Cr alloy and deposition of PbO at low temperature parts occured in the first loop corrosion test. These caused plugging of the narrow passage in electro-magnetic pumu(EMP) system. Adoption of filters and a wide passage in an EMP system, and the use of an inner-polished tube specimen brought about a good effect.

Journal Articles

Recent activities of Pb-Bi technology for ADS at JAERI

Kikuchi, Kenji; Saito, Shigeru; Kurata, Yuji; Futakawa, Masatoshi; Sasa, Toshinobu; Oigawa, Hiroyuki; Umeno, Makoto*; Mori, Keijiro*; Takano, Hideki; Wakai, Eiichi

Proceedings of 11th International Conference on Nuclear Engineering (ICONE-11) (CD-ROM), 7 Pages, 2003/04

In order to construct ADS Target Test facility in J-PARC project the research and development on Pb-Bi technology have been carried, which cover target design with computer simulation, flowing loop test, stagnant corrosion test, oxygen sensor and cleaning techniques. Obtained results are as follows: Corrosion rate of SUS316 under flowing Pb-Bi at 1m/s at 450$$^{circ}$$C is 0.1 mm / 3000 hrs. Fe and Cr were melted into lead bismuth from SS316 in the high temperature part and deposited in the low-temperature part according to the difference of solubility. The corrosion thickness decreases with increasing Cr content in the stagnant corrosion test at saturated oxygen concentration. Reliable oxygen sensors are to be developed by using suitable reference electrodes. As a result of cleaning tests, blushing process was needed to remove Pb-Bi effectively after immersion in the silicon oil. The mixed acid easily dissolved Pb-Bi and removed almost perfectly. But specimens themselves were affected by coloring.

Journal Articles

Corrosion studies in liquid Pb-Bi alloy at JAERI; R&D program and first experimental results

Kurata, Yuji; Futakawa, Masatoshi; Kikuchi, Kenji; Saito, Shigeru; Osugi, Toshitaka

Journal of Nuclear Materials, 301(1), p.28 - 34, 2002/02

 Times Cited Count:48 Percentile:93.88(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Experiments for accelerator driven nuclear transmutation under the JAERI-KEK joint project of high intensity proton accelerator

Ikeda, Yujiro; Oigawa, Hiroyuki; Sasa, Toshinobu

Purazuma, Kaku Yugo Gakkai-Shi, 77(11), p.1128 - 1134, 2001/11

no abstracts in English

JAEA Reports

Investigation of corrosion, water reaction, polonium evaporation and bismuth resource in liquid metal lead-bismuth technology

Takano, Hideki; Takizuka, Takakazu; Kitano, Teruaki*

JAERI-Review 2000-014, 134 Pages, 2000/10

JAERI-Review-2000-014.pdf:13.43MB

no abstracts in English

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