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Journal Articles

Behavior of high-burnup advanced LWR fuels under accident conditions

Amaya, Masaki; Udagawa, Yutaka; Narukawa, Takafumi; Mihara, Takeshi; Taniguchi, Yoshinori

Proceedings of Annual Topical Meeting on LWR Fuels with Enhanced Safety and Performance (TopFuel 2016) (USB Flash Drive), p.53 - 62, 2016/09

In order to evaluate adequacy of present safety criteria and safety margins in terms of advanced fuels and provide a database for future regulation on them, JAEA started an extensive research program called ALPS-II program, which has been sponsored by NRA, Japan. This program is primarily composed of tests simulating a RIA and a LOCA on the high-burnup advanced fuels irradiated in commercial PWR or BWR. Recently, the failure limits of the high-burnup advanced fuels under RIA conditions were investigated at NSRR, and post-test examinations on the fuel rods after the pulse irradiation tests are being performed. In terms of the simulated LOCA test, integral thermal shock tests and high temperature oxidation tests were carried out at RFEF, and the fracture limits, high temperature oxidation rate, etc. of the high-burnup advanced fuel cladding were investigated. This paper mainly describes some recent experimental results obtained in this program with respect to RIA and LOCA.

JAEA Reports

Radiochemical studies of iodine, tritium and neptunium

Saeki, Masakatsu

JAERI-Review 2004-011, 54 Pages, 2004/03

JAERI-Review-2004-011.pdf:5.21MB

In this review, experimental results on studies of radioactive iodine, tritium and neptunium are summarized. On studies of radioactive iodine, from various experimental results, the process establishing the formation mechanism of organic iodides was fully described. On the basis of formation mechanism, possibilities for the formation of organic iodides under nuclear reactor accidents and so on were also discussed. On studies of tritium, three topics were concisely described on the isotopic composition of tritium gases, the chemical forms and the diffusivity of tritium in various materials, and the sorption and desorption behaviors of tritium on surfaces of various materials. On the neptunium chemistry, the relationship between the structure of neptunium compound and the Moessbauer isomer shift and experimental results on neptunyl(VI) hydroxides were discussed.

Journal Articles

Development of remote surveillance squad

Kobayashi, Tadayoshi; Miyajima, Kazutoshi; Yanagihara, Satoshi

Gekkan Shobo, 23(6), p.22 - 26, 2001/06

no abstracts in English

JAEA Reports

Development of sodium facilities for NSRR fast reactor fuel tests, 2; Sodium capsule

Yoshinaga, Makio; Nakamura, Takehiko; Yamazaki, Toshi*

JAERI-Tech 2000-017, p.59 - 0, 2000/03

JAERI-Tech-2000-017.pdf:2.31MB

no abstracts in English

Journal Articles

Small-scale component experiments of the penetration leak characterization test in the ALPHA program

Yamano, Norihiro; Sugimoto, Jun; Maruyama, Yu; Hidaka, Akihide; Kudo, Tamotsu; Soda, Kunihisa

Nuclear Engineering and Design, 145(3), p.365 - 374, 1993/12

 Times Cited Count:2 Percentile:29.78(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Centralized environmental radiation monitoring system in JAERI

; Kobayashi, Hideo

Proc. of Asia Congress on Radiation Protection, p.199 - 202, 1993/00

no abstracts in English

JAEA Reports

Silicone resin experiments of EPA leak characterization test in the ALPHA program(SLB001,SLB002); Evaluation of thermal effect on silicone resin behavior

Yamano, N.; Sugimoto, Jun; Maruyama, Yu; Hidaka, Akihide; Soda, Kunihisa

JAERI-M 92-055, 14 Pages, 1992/03

JAERI-M-92-055.pdf:0.83MB

no abstracts in English

Journal Articles

Small-scale penetration leak test in ALPHA program

Yamano, N.; Sugimoto, Jun; Maruyama, Yu; Hidaka, Akihide; Soda, Kunihisa

NUREG/CP-0120, p.439 - 455, 1992/00

no abstracts in English

Journal Articles

Development of accident consequence assessment code at JAERI

Homma, Toshimitsu; Togawa, Orihiko; *

EUR-13013-2, p.1049 - 1063, 1991/00

no abstracts in English

JAEA Reports

Introduction and preparation of the nuclear fuel cycle facility risk analysis code, STAR

Nomura, Yasushi

JAERI-M 90-158, 53 Pages, 1990/09

JAERI-M-90-158.pdf:1.36MB

no abstracts in English

Journal Articles

Radiation-induced conductivity in polymeric insulating materials degraded under specified conditions

; Kuriyama, Isamu; *; *

IEEE Transactions on Electrical Insulation, 17(4), p.306 - 313, 1982/00

no abstracts in English

JAEA Reports

Oral presentation

Study on improvement of safety for accident conditions in spent fuel pool, 1; Whole plan

Kaji, Yoshiyuki; Nemoto, Yoshiyuki; Takase, Kazuyuki; Tojo, Masayuki*; Goto, Daisuke*; Iwata, Yutaka*; Otake, Yukihiko*; Nishimura, Satoshi*; Suzuki, Hiroaki*

no journal, , 

We will make quantitatively clear the phenomenon of fuel air oxidation mechanism, fuel failure mechanism after loss of coolant and criticality risks during and after sever accidents of Spent Fuel Pool(SFP) and clarify the quantitative effects of enhancements of SFP safety such as Spray and fuel loading patterns. We will report the whole plan in this presentation.

Oral presentation

Study on improvement of safety for accident conditions in spent fuel pool, 3; Evaluation of decay heat and cladding temperature during accident

Kobayashi, Kensuke*; Goto, Daisuke*; Tojo, Masayuki*; Ikehara, Tadashi*; Kaji, Yoshiyuki; Nemoto, Yoshiyuki

no journal, , 

We evaluate fuel temperature based on the steady state heat transfer analysis with considering accurate fuel history and storage conditions.

Oral presentation

Study on improvement of safety for accident conditions in spent fuel pool, 6; Issues and procedures on the effectiveness evaluation for SFP safety measures

Chitose, Hiromasa*; Watanabe, Satoshi*; Sadamatsu, Hideaki*; Iwata, Yutaka*; Kaji, Yoshiyuki; Nemoto, Yoshiyuki

no journal, , 

We researched the recent enhancements of regulations and solutions related Spent Fuel Pool safety and reported the analytical results about problems and evaluation procedures related effectiveness evaluation of safety measures.

Oral presentation

Study on cladding oxidation behavior on spent fuel pool severe accident, 2

Nemoto, Yoshiyuki; Kaji, Yoshiyuki; Ogawa, Chihiro; Nakashima, Kazuo*; Tojo, Masayuki*; Kanazawa, Toru*; Goto, Daisuke*

no journal, , 

In order to investigate the air oxidation behavior of cladding materials for study on improvement of safety in spent fuel pool loss of coolant accident condition, both isothermal oxidation tests by short length specimens and oxidation tests with temperature gradient by long length specimens were conducted and the knowledge on influence of temperature and air flow rate on cladding oxidation behavior was obtained in this study.

Oral presentation

Study on improvement of safety for accident conditions in spent fuel pool, 27; Improvement of SAMPSON code and evaluation of cooling characteristics of SFP spray

Suzuki, Hiroaki*; Morita, Yoshihiro*; Naito, Masanori*; Kaji, Yoshiyuki; Nemoto, Yoshiyuki

no journal, , 

Severe accident code SAMPSON was upgraded by introducing the models of Zr oxidation in air, and spray cooling, etc, in this study. Analytical results on spent fuel pool (SFP) accident were obtained and effectiveness of the spray cooling system for the safety measure of the SFP was discussed in this study.

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