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Journal Articles

Super ODS steels R&D for fuel cladding of next generation nuclear systems, 1; Introduction and alloy design

Kimura, Akihiko*; Kasada, Ryuta*; Iwata, Noriyuki*; Kishimoto, Hirotatsu*; Zhang, C. H.*; Isselin, J.*; Dou, P.*; Lee, J. H.*; Muthukumar, N.*; Okuda, Takanari*; et al.

Proceedings of 2009 International Congress on Advances in Nuclear Power Plants (ICAPP '09) (CD-ROM), p.9220_1 - 9220_8, 2009/05

Cladding material development is essential for realization of highly efficient high burn-up operation of next generation nuclear systems, where high performance is required for the materials, that is, high strength at elevated temperature, high resistance to corrosion and high resistance to irradiation. Oxide dispersion strengthening (ODS) ferritic steels are considered to be most adequate for the cladding material because of their high strength at elevated temperature. In this work, "Super ODS steel" that has better corrosion resistance than 9Cr-ODS steel, has been developed for application to cladding of a variety of next generation nuclear systems. In the following ten papers, the recent experimental results of "Super ODS steel" R&D will be presented, indicating that many unexpected preferable features were found in the mechanical properties of nano-sized oxide dispersion high-Cr ODS ferritic steel. A series of paper begins with alloy design of "Super ODS steel". Corrosion issue requires Cr concentration more than 14wt.%, but aging embrittlement issue requires less than 16wt.%. An addition of 4wt.%Al is effective to improve corrosion resistance of 16wt.%Cr-ODS steel in supercritical water (SCW) and lead-bismuth eutectic (LBE), while it is detrimental to high-temperature strength. Additions of 2wt.%W and 0.1wt.%Ti are necessary to keep high strength at elevated temperatures. An addition of small amount of Zr or Hf results in a significant increase in creep strength at 700 $$^{circ}$$C in Al added ODS steels. Tube manufacturing was successfully done for the super ODS steel candidates. "Super ODS steel" is promising for the fuel cladding material of next generation nuclear systems, and the R&D is now ready to proceed to the next stage of empirical verification.

Journal Articles

Super ODS steels R&D for fuel cladding of next generation nuclear systems, 6; Corrosion behavior in SCPW

Lee, J. H.*; Kimura, Akihiko*; Kasada, Ryuta*; Iwata, Noriyuki*; Kishimoto, Hirotatsu*; Zhang, C. H.*; Isselin, J.*; Dou, P.*; Muthukumar, N.*; Okuda, Takanari*; et al.

Proceedings of 2009 International Congress on Advances in Nuclear Power Plants (ICAPP '09) (CD-ROM), p.9223_1 - 9223_6, 2009/05

Corrosion is a critical issue for cladding materials, especially, in sever corrosion environment as supercritical pressurized water (SCPW). In this work, the effects of alloy elements on the corrosion behavior in SCPW were investigated for a series of oxide dispersion strengthened (ODS) steels to design alloy compositions for corrosion resistant super ODS ferritic steels. Corrosion tests were carried out for the ODS steels with different concentrations of Cr and Al in SCPW at 773 K at 25 MPa with 8 ppm of dissolved oxygen. The corrosion rate of SUS430, which contained 16wt.%Cr, was much higher than 16Cr-ODS steel. This suggests that nano-sized oxide particles dispersion and very fine grains play an important role in suppression of the corrosion. The corrosion of the ODS steel was reduced by an addition of Al in 16wt.%Cr-ODS steel but not in 19Cr-ODS steel. FE-EPMA chemical analysis clearly indicated that the surface of the Al added ODS steels was covered by alumina which suppresses the corrosion in SCPW. It is considered that an adequate combination of the contents of Cr and Al is ranging (14-16)Cr and (3.5-4.5)Al.

Journal Articles

Super ODS steels R&D for fuel cladding of next generation nuclear systems, 5; Mechanical properties and microstructure

Kasada, Ryuta*; Lee, S. G.*; Lee, J. H.*; Omura, Takamasa*; Zhang, C. H.*; Dou, P.*; Isselin, J.*; Kimura, Akihiko*; Inoue, Masaki; Ukai, Shigeharu*; et al.

Proceedings of 2009 International Congress on Advances in Nuclear Power Plants (ICAPP '09) (CD-ROM), p.9072_1 - 9072_5, 2009/05

The newly-developed Al-added ODS ferritic steels with an addition of Zr or Hf, socalled super ODS candidate steels, showed good notch-impact properties in the as-received condition with keeping the excellent creep strength.

Oral presentation

Effect of zirconium on the microstrusture and mechanical properties of high-Cr ODS ferritic steels

Dou, P.*; Kasada, Ryuta*; Kimura, Akihiko*; Okuda, Takanari*; Inoue, Masaki; Ukai, Shigeharu*; Onuki, Somei*; Fujisawa, Toshiharu*

no journal, , 

Oral presentation

High density configuration experiment of noble gas measurement systems in Japan

Beziat, G.*; Kalinowski, M.*; Inoue, Naoko; Kusmierczyk-Michulec, J.*; Bar$'e$, J.*; Gheddou, A.*; Bourgouin, P.*; Yamamoto, Yoichi; Tomita, Yutaka

no journal, , 

In early 2018, two mobile noble gas measurement systems were deployed and have started measurement at Horonobe and Mutsu in Japan. Together with a third mobile system that will be deployed at Fukuoka, Japan, in spring 2019, and the operating IMS noble gas system at station RN38, Takasaki, Japan, this creates a high density configuration of noble gas measurement systems. The objective of this configuration is to generate a database of detections which will be used to develop and test methods for better understanding the contributions of known sources from across Eurasia. Contributions from these sources are frequently observed at IMS station RN38. The high density configuration will provide a framework to test and optimize source location algorithms and to better understand level C episodes, specifically at JPX38. The three mobile noble gas measurement systems used in this experiment and their operation are externally funded. The planned duration of this experiment is two years.

Oral presentation

Argon-37 variability in the low troposphere

Purtschert, R.*; Kalinowski, M.*; Riedmann, R.*; Fontaine-Lagrand, J.-E.*; Kusmierczyk-Michulec, J.*; Gheddou, A.*; Bourgouin, P.*; Tomita, Yutaka

no journal, , 

Argon-37 ($$^{37}$$Ar) is produced in the high troposphere by spallation of argon through $$^{40}$$Ar(n,4n)$$^{37}$$Ar and by neutron capture, $$^{36}$$Ar(n,$$gamma$$)$$^{37}$$Ar. The resulting natural equilibrium concentration of $$^{37}$$Ar in the mixed troposphere is about 0.5-1 mBq/m$$^{3}$$. This value may define the background level for the use of $$^{37}$$Ar for search area reduction by means of atmospheric $$^{37}$$Ar measurements in downwind direction of a potential test area in the course of an OSI. In order to investigate long term atmospheric activity levels of $$^{37}$$Ar, bulk air samples were collected close to the CTBTO IMS Radionuclide station located in Takasaki, Japan. In the years 2016-2018 in total 105 air samples were taken and analyzed for their $$^{37}$$Ar activity concentrations with no value exceeding 10 mBq/m$$^{3}$$.

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