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JAEA Reports

JAERI-JNC joint research report; A Study on degradation of structural materials used under the irradiation environment in nuclear reactors

Ueno, Fumiyoshi; Nagae, Yuji*; Nemoto, Yoshiyuki; Miwa, Yukio; Takaya, Shigeru*; Hoshiya, Taiji*; Tsukada, Takashi; Aoto, Kazumi*; Ishii, Toshimitsu; Omi, Masao; et al.

JAERI-Research 2005-023, 132 Pages, 2005/09

JAERI-Research-2005-023.pdf:33.03MB

JAERI and JNC have started a JAERI-JNC joint research program in fiscal year 2003, which has been aimed for efficient progress and synergistic effect on the research activities in both Institutes. This study has been chosen one of the joint research themes because it has been our common objective in the field of structural materials of FBR and LWR components. The purpose of the study is to clarify damage mechanism of structural materials used under irradiation, and then to develop the methods for damage evaluation and detection in earlier stage of progressing process of damage. In fiscal year 2004 and 2005, micro-corrosion measurement, electrochemical corrosion test and leakage magnetic flux density measurement apparatuses were developed and equipped in two hot facilities and irradiated and unirradiated crept specimens, irradiated high purity model austenitic stainless alloys were also prepared and applied to this study. These apparatuses and specimens were used for damage evaluation, and these feasibilities for nuclear power plant materials were studied.

JAEA Reports

JNC-JAERI united research report; A Study on degradation of structural materials under irradiation environment in nuclear reactors (Joint research)

Hoshiya, Taiji*; Ueno, Fumiyoshi; Takaya, Shigeru*; Nagae, Yuji*; Nemoto, Yoshiyuki; Miwa, Yukio; Aoto, Kazumi*; Tsukada, Takashi; Abe, Yasuhiro*; Nakamura, Yasuo*; et al.

JAERI-Research 2004-016, 53 Pages, 2004/10

JAERI-Research-2004-016.pdf:22.07MB

Japan Nuclear Cycle Development Institute (JNC) and Japan Atomic Energy Research Institute (JAERI) have started a JNC-JAERI united research program cooperatively in 2003, which has been aimed for efficient progress and synergistic effect on the research activities of both Institutes in order to lead the facing task of unification between JNC and JAERI. This study has been chosen one of the united research themes, and the purpose of it is to clarify damage mechanism of structural materials under irradiation, and then to develop the methods for damage evaluation and detection in earlier stage of progressing process of damage. In fiscal year 2003, magnetic flux density distribution (JNC) and micro-corrosion (JAERI) measurement apparatus were newly developed and equipped in Hot Facilities in two Institutes, respectively. These apparatus were designed and produced in consideration of radiation resistance and remote-controlled operation to equip in hot cells. We will start the study on neutron irradiation damage by employing the two apparatus as the next step.

JAEA Reports

Investigation of the properties of high temperature resistance alloys used in the helium gas cooled high temperature reactor

Uwaba, Tomoyuki

JNC-TN9420 2000-005, 28 Pages, 2000/03

JNC-TN9420-2000-005.pdf:0.94MB

In the first phase of the feasibility study, their basic objectives are presentating the feasible image and scenario of development of the FBR cycle system, which is composed of the fast reactor, spent fuel reprocessing and fuel manufacturing facility. In the development of the FBR system in this phase, various ideas of plants are to be studied, which include coolant types such as sodium, heavy metals, gases(CO$$_{2}$$, He), wator, and middle or small size of the reactor, and fuel types (MOX, metal and nitride). In this report, as a part of this study, materials used for the core of the helium gas cooled reactor and their integrity (corrosion, mechanical and irradiation property) under high temperature helium atmosphere were investigated from open literatures.

JAEA Reports

The survey and evaluation of oxidation for core material of the austenitic stainless steels in carbon dioxide gas-cooled reactor

Mizuta, Shunji; ;

JNC-TN9400 2000-032, 38 Pages, 2000/03

JNC-TN9400-2000-032.pdf:1.2MB

lt is necessary for feasibility study of fast reactor to evaluate the oxidation of the austenitic stainless steels in the case of using for core material in carbon dioxide gas-cooled reactor. The properties for oxidation of austenitic stainless steels in carbon dioxide were surveyed in literatures and the data were selected after evaluation of factors for oxidation in carbon dioxide. The equation of oxidation in carbon dioxide for PE16, 20Cr/25Ni/Nb, 18Cr-8Ni and JNC Cladding materials were proposed. The equation for oxidation of austenitic stainless steels were expressed as upper limit for the equation according to parabolic law. The equation for JNC cladding materials (PNC316, PNC1520, 14Cr-25Ni) was proposed based the oxidation behavior of 18Cr-8Ni which is same oxidation region for weight gain in three-component system of Fe-Cr-Ni, in addition to evaluate of effect for silicon content. The oxidation equation of 20Cr/25Ni/Nb was applied to the high Ni alloy of JNC cladding material. The obtained equation is as follows, X = 4.4W$$times$$1000, W = $$sqrt{(kp・t)}$$, kp = $$alpha$$ exp(-Q/(RT)), X: oxide thickness[$$mu$$m], W : weight gain[g$$times$$cm$$^{-2}$$], kp : parabolic rate constant[g$$^{2}$$$$times$$cm$$^{-4}$$$$times$$ s$$^{-1}$$], t :time[sec] $$alpha$$ : constant[g$$^{2}$$$$times$$cm$$^{-1}$$$$times$$S$$^{-1}$$], Q : activation energy[J・mol$$^{-1}$$], R : gas constant[8.314J $$times$$K$$^{-5}$$ $$times$$mol$$^{-1}$$], T : temperature[K] (1) PE16 : kp = 1.090$$times$$10$$^{-3}$$ exp(-192,500/(RD)), (2) 20Cr/25Ni/Nb : kp = 1.651$$times$$10$$^{-2}$$ exp(-201,300/(RT)) High Ni alloy (JNC), (3)18Cr-8Ni : kp = 1.503$$times$$10$$^{-8}$$ exp(-60,000/(RT)), (4) PNC316, PNC1520 : kp = 1.503$$times$$10$$^{-8}$$ exp(-60,000/(RT))$$times$$0.62$$^{2}$$ 14Cr-25Ni(JNC) The weight gain is (3)$$rangle$$(4)$$rangle$$(2)$$rangle$$(1) in order.

JAEA Reports

Studies on the Quality Optimization of Hastelloy Alloy XR

Kondo, Tatsuo; ; *; *; *; ; ; ; *

JAERI-M 86-003, 228 Pages, 1986/02

JAERI-M-86-003.pdf:44.86MB

no abstracts in English

Oral presentation

Corrosion property of sheath materials using MI cables at conditions simulated severe accident

Nakano, Hiroko; Shibata, Hiroshi; Takeuchi, Tomoaki; Matsui, Yoshinori; Tsuchiya, Kunihiko

no journal, , 

no abstracts in English

Oral presentation

Corrosion property of sheath materials using MI cables at conditions simulated severe accident, 2

Nakano, Hiroko; Hirota, Noriaki; Takeuchi, Tomoaki; Shibata, Hiroshi; Nemoto, Tadahiro*; Hanamoto, Yukio*; Tsuchiya, Kunihiko

no journal, , 

no abstracts in English

Oral presentation

Corrosion behavior of sheath materials using signal cables under light water reactor severe accident environment, 2

Nakano, Hiroko; Hirota, Noriaki; Takeuchi, Tomoaki; Shibata, Hiroshi; Nemoto, Tadahiro*; Hanamoto, Yukio*; Tsuchiya, Kunihiko

no journal, , 

no abstracts in English

Oral presentation

Corrosion property of sheath materials using MI cables at conditions simulated severe accident, 3

Nakano, Hiroko; Hirota, Noriaki; Takeuchi, Tomoaki; Tsuchiya, Kunihiko

no journal, , 

no abstracts in English

Oral presentation

Corrosion properties of PCV equivalent materal for simulated severe accident

Nakano, Hiroko; Takeuchi, Tomoaki; Otsuka, Kaoru; Hirota, Noriaki; Tsuchiya, Kunihiko

no journal, , 

no abstracts in English

Oral presentation

Corrosion behavior of Ni-based alloy in molten FLiNaK salt as a fundamental research on molten salt reactors

Ogasawara, Koji*; Sekiguchi, Yuma*; Terai, Takayuki*; Kawamura, Hiroshi*; Tsuchiya, Kunihiko; Watanabe, Takashi*

no journal, , 

no abstracts in English

Oral presentation

Corrosion property of PCV equivalent material under various gas conditions containing iodine gas

Nakano, Hiroko; Takeuchi, Tomoaki; Hirota, Noriaki; Tsuchiya, Kunihiko

no journal, , 

no abstracts in English

12 (Records 1-12 displayed on this page)
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