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Journal Articles

Polarization characteristics and evaluation of corrosion rate of stainless steel in nitric acid solution containing $$^{237}$$Np

Irisawa, Eriko; Kato, Chiaki; Yamashita, Naoki; Sano, Naruto

Zairyo To Kankyo, 71(3), p.70 - 74, 2022/03

In order to evaluate the corrosion of stainless steels used in spent nuclear fuel reprocessing facilities, the immersion corrosion tests and polarization measurements were performed using R-SUS304ULC stainless steel in nitric acid solution containing a kind of radionuclides, $$^{237}$$Np. At temperatures above 328 K, the corrosion potential was higher than that in nitric acid solution and was near the transpassive region. From the comparison between the corrosion amount calculated by the immersion corrosion tests and the polarization resistance, the values of $$k$$=0.018-0.025 V were obtained as a conversion factor, and the possibility of calculating the corrosion amount from the electrochemical measurement was examined.

Journal Articles

An Experimental investigation of influencing chemical factors on Cs-chemisorption behavior onto stainless steel

Nishioka, Shunichiro; Nakajima, Kunihisa; Suzuki, Eriko; Osaka, Masahiko

Journal of Nuclear Science and Technology, 56(11), p.988 - 995, 2019/11

 Times Cited Count:12 Percentile:79.53(Nuclear Science & Technology)

In order to contribute to improvement of Cs chemisorption model used in severe accident analysis codes, the influence of chemical factors (temperature, atmosphere, concentration of affecting chemical elements etc.) on the Cs chemisorption behaviour onto stainless steel was investigated experimentally. It was found that the surface reaction rate constant used in the current Cs-chemisorption model was influenced by not only temperature, as already known, but also atmosphere, cesium hydroxide (CsOH) concentration in the gas phase and silicon content in SS304. Such chemical factors should be considered for the construction of the improved Cs-chemisorption model. Another important finding is that the chemisorption behavior at lower temperatures, around 873 K, could differ from those above 1073 K. Namely, Cs-Fe-O compounds would form as the main Cs-chemisorbed compounds at 873 K while Cs-Si-Fe-O compounds at more than 1073 K.

JAEA Reports

Report of Examination of the Sample from Core Shroud (O1-H2) at Onagawa Nuclear Power Station Unit-1 (Contract research)

The Working Team for Examination of the Sample from Core Shrouds and Primary Loop Recirculation Pipi

JAERI-Tech 2004-012, 62 Pages, 2004/02

JAERI-Tech-2004-012.pdf:16.4MB

At Onagawa Nuclear Power Station Unit-1 of the Tohoku Electric Power co., inc., cracks were confirmed near welded joints of core shroud in 15th periodical inspection. Tohoku Electric Power co., inc. has conducted a material examination with Nippon Nuclear Fuel Development Co., Ltd.. To investigate independently, a JAERI's own evaluation report was provided. The results are as follows; (1) Hardening layer was detected at the depth of about 150-250$$mu$$m from outer surface of the sample. (2) Corrosion products were observed on inner surface of the cracks and some of them penetrated into grains. (3) Transgranular cracking and intergranular cracking were observed at the region within about 100$$mu$$m and the deeper region more than about 200$$mu$$m in depth from outer surface of the sample, respectively. (4) Distinct chromium depletion was not detected at the grain boundaries. (5) Chemical compositions of the sample corresponded to type 304L stainless steel in Japanese Industrial Standard. From the above, it is concluded that the cracks are stress corrosion cracking.

Journal Articles

In-pile and post-irradiation creep of type 304 stainless steel under different neutron spectra

Kurata, Yuji; Itabashi, Yukio; Mimura, Hideaki*; Kikuchi, Taiji; Amezawa, Hiroo; Shimakawa, Satoshi; Tsuji, Hirokazu; Shindo, Masami

Journal of Nuclear Materials, 283-287(Part.1), p.386 - 390, 2000/12

 Times Cited Count:6 Percentile:42.55(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Neutronics analysis on helium production control in stainless steel by neutron spectral tailoring in the JMTR

Shimakawa, Satoshi; ; Nagao, Yoshiharu;

JAERI-Tech 95-023, 26 Pages, 1995/03

JAERI-Tech-95-023.pdf:1.08MB

no abstracts in English

Journal Articles

Oxidation of 304 stainless steel in high-temperature steam

; ; Yaguchi, Shinnosuke*

Journal of Nuclear Materials, 140, p.74 - 84, 1986/00

 Times Cited Count:21 Percentile:86.83(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Ductile fracture behavior of circumferentially cracked type 304 stainless steel piping under bending load

; ; *; *

Nucl.Eng.Des., 94, p.221 - 231, 1986/00

 Times Cited Count:6 Percentile:58.99(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Fatigue and fracture behavior of straight pipe with flaws in inner surface

; ; ; *;

Nucl.Eng.Des., 66(1), p.33 - 45, 1981/00

 Times Cited Count:2 Percentile:36.87(Nuclear Science & Technology)

no abstracts in English

Journal Articles

High Velocity Tensile Test of JIS TYPE SUS304; Stainless Steel at Elevated Temperatures

; ; Ueda, Shuzo

Nihon Kikai Gakkai Rombunshu, A, 42(359), p.2034 - 2041, 1976/00

no abstracts in English

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