Irradiation assisted stress corrosion cracking of austenitic stainless steels

Tsukada, Takashi

JAERI-Research 98-007, 187 Pages, 1998/03

JAERI-Research-98-007.pdf:17.46MB

no abstracts in English

Study of through-thickness attenuation of irradiation embrittlement using JPDR pressure vessel

Suzuki, Masahide;

JAERI-Research 94-038, 23 Pages, 1994/11

JAERI-Research-94-038.pdf:0.87MB

no abstracts in English

Neutron activation analysis of deposition samples in Tokai-mura, Japan and evaluation of resuspension of Cs

Ueno, Takashi; Amano, Hikaru; Kobayashi, Yoshii

Hoken Butsuri, 29(1), p.17 - 22, 1994/03

https://doi.org/10.5453/jhps.29.17

no abstracts in English

None

Kawamura, Kazuo*; Nakajima, Tatsuya*; Tomori, Masahiko*

PNC TJ7361 93-004, 91 Pages, 1993/03

PNC-TJ7361-93-004.pdf:8.99MB

no abstracts in English

Sealing performance test for main flange of pressure vessel of T test section in HENDEL

Ioka, Ikuo; *; Inagaki, Yoshiyuki; *; ; Suzuki, Kunihiro;

JAERI-M 90-221, 21 Pages, 1990/12

JAERI-M-90-221.pdf:0.68MB

no abstracts in English

Study to evaluate leaching mass of elements from damaged fuels, 1; Leaching behavior of multiphase molten debris in the system of stainless steel and zircaloy

Ikeuchi, Hirotomo; Yano, Kimihiko; Watanabe, Masayuki; Koizumi, Kenji

no journal, , 

no abstracts in English

Predict form change of fuel debris; Study on physical mechanism in aging phenomenon of fuel debris

Suzuki, Seiya; Yano, Kimihiko; Watanabe, Masayuki; Koizumi, Kenji

no journal, , 

no abstracts in English

Study on physical mechanism in aging phenomenon of fuel debris, 3; Transition of total crack length by cyclic temperature fluctuation under water in solidified molten materials

Suzuki, Seiya; Arai, Yoichi; Okamura, Nobuo; Watanabe, Masayuki

no journal, , 

Clarification of aging phenomenon of fuel debris is one of the important issues because to evaluate that the safety during long term at defueling and storing. As a physical mechanism, we were investigated the effect of environmental temperature on the amount of cracks increased, and clarified the behavior of crack generation and propagation in submerged fuel debris.

Research on the stability of fuel debris consisting of oxides and alloys, 12; Chemical state analysis and stability evaluation for oxidative degradation of the simulated debris

Watanabe, Masayuki; Kumagai, Yuta; Kusaka, Ryoji; Nakada, Masami; Akiyama, Daisuke*; Kirishima, Akira*; Sato, Nobuaki*; Sasaki, Takayuki*

no journal, , 

Metal-alloyed debris would be formed by the reaction of nuclear fuels with the zircaloy cladding, control rods, and other reactor structural materials such as stainless steel (SUS) at high temperature at the Fukushima Daiichi Nuclear Power Plant in Japan. The chemical reaction and the dissolution behavior from the surface on the debris are required for the evaluation of the chemical stability on the debris under the reactor environment. In this study, immersion tests of some simulated debris synthesized by UO, SUS and zirconium into water or hydrogen peroxide and quantitative analysis of solution were performed. Laser spectroscopy and Mssbauer spectroscopy were also employed for the evaluation of chemical evolution of the simulated debris resulting of immersion tests.

Study on physical mechanism in phenomenon of fuel debris

Suzuki, Seiya; Arai, Yoichi; Okamura, Nobuo; Watanabe, Masayuki

no journal, , 

Clarification of aging phenomenon of fuel debris is one of the important issues because to evaluate that the safety during long term at defueling and storing. As a physical mechanism, we were investigated the effect of environmental temperature on the amount of cracks increased, and clarified the behavior of crack generation and propagation in fuel debris.