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Journal Articles

BWR lower head penetration failure test focusing on eutectic melting

Yamashita, Takuya; Sato, Takumi; Madokoro, Hiroshi; Nagae, Yuji

Annals of Nuclear Energy, 173, p.109129_1 - 109129_15, 2022/08

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

Journal Articles

Modeling for evaluation of debris coolability in lower plenum of reactor pressure vessel

Maruyama, Yu*; Moriyama, Kiyofumi; Nakamura, Hideo; Hirano, Masashi; Nakajima, K.*

Journal of Nuclear Science and Technology, 40(1), p.12 - 21, 2003/01

 Times Cited Count:6 Percentile:41.75(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Validation of CAMP code for thermo-fluiddynamics of molten debris in lower Plenum

Maruyama, Yu; Moriyama, Kiyofumi; Nakamura, Hideo; Hashimoto, Kazuichiro; Hirano, Masashi; Nakajima, K.*

Proceedings of RASPLAV Seminar 2000 (CD-ROM), 8 Pages, 2000/11

no abstracts in English

JAEA Reports

Fundamental experiments on accumulation behavior of molten fuel in a pressure vessel lower head

Shibamoto, Yasuteru; Nakamura, Hideo; Anoda, Yoshinari; Kukita, Yutaka*

JAERI-Tech 99-042, 41 Pages, 1999/05

JAERI-Tech-99-042.pdf:3.36MB

no abstracts in English

Journal Articles

Visualization of simulated molten-fuel behavior in a pressure vessel lower head using high-frame-rate neutron radiography

Nakamura, Hideo; Shibamoto, Yasuteru; Anoda, Yoshinari; Kukita, Yutaka*; Mishima, Kaichiro*; Hibiki, Takashi*

Nuclear Technology, 125(2), p.213 - 224, 1999/02

 Times Cited Count:8 Percentile:53.62(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Research plan on in-vessel debris coolability in ALPHA program

Maruyama, Yu; Yamano, Norihiro; Kudo, Tamotsu; Moriyama, Kiyofumi; Sugimoto, Jun

JAERI-memo 08-127, p.269 - 275, 1996/06

no abstracts in English

Journal Articles

High-frame-rate video visualization of simulated lower head behavior during TMI accident using neutron radioscopy

Nakamura, Hideo; Shibamoto, Yasuteru; Anoda, Yoshinari; Kukita, Yutaka; Mishima, Kaichiro*; Hibiki, Takashi*

Fifth World Conf. on Neutron Radiography, 0, p.665 - 672, 1996/00

no abstracts in English

Journal Articles

In-vessel debris coolability experiments in ALPHA program

Maruyama, Yu; Yamano, N.; Moriyama, Kiyofumi; H.S.Park*; Kudo, Tamotsu; Sugimoto, Jun

Proc. of Int. Topical Meeting on Probabilistic Safety Assessment (PSA96), 3, p.1367 - 1374, 1996/00

no abstracts in English

JAEA Reports

Gamma spectrometry of TMI-2 debris

Uetsuka, Hiroshi; Nagase, Fumihisa; *

JAERI-Research 95-084, 36 Pages, 1995/11

JAERI-Research-95-084.pdf:1.32MB

no abstracts in English

Journal Articles

Present status of research related to in-vessel debris coolability and experimental plan in ALPHA program at JAERI

Maruyama, Yu; Yamano, N.; Kudo, Tamotsu; Moriyama, Kiyofumi; Sugimoto, Jun

Proc., Seminar on the Vapor Explosions in Nuclear Power Safety,Kanzanji 1995, 0, p.54 - 69, 1995/00

no abstracts in English

Oral presentation

Failure evaluation analysis of reactor pressure vessel lower head of BWR in a severe accident

Kaji, Yoshiyuki; Katsuyama, Jinya; Yamaguchi, Yoshihito; Nemoto, Yoshiyuki; Abe, Yosuke; Nagase, Fumihisa

no journal, , 

In existing severe accident code, rupture of reactor pressure vessel (RPV) lower head after melt down of core is analyzed using the simple model like the Larson-Miller model. It is difficult to evaluate the local deformation and rupture behavior for the actual lower head with such a simple model. Therefore, in order to predict the real position of molten fuel outside pressure vessel, it is necessary to evaluate rupture time and rupture behavior of RPV lower head of BWR precisely.Re-evaluation of materials data such as mechanical properties, creep deformation/rupture properties is made for low alloy steel, Ni-based alloy and stainless steels based on past research activities. To expand materials database and verify the creep constitutive equation and rupture model, we started obtaining the materials data under uniaxial and multi-axial stress conditions at high temperature near melting point. To investigate the inhomogeneous temperature and stress distribution by geometrical complex of BWR lower head, the detailed 3D model of RPV lower head with control rod guide tubes (CRGTs) and shroud supports are constructed and the 3D thermal hydraulic analysis of simulated molten pool and creep deformation analysis of lower head are performed using ANSYS Fluent / Mechanical finite element code. It is found that the possibility of failure mode for BWR lower head are both the penetration failure which is melt-through or drop-away of the guide tube, local rupture and global rupture of lower head by creep deformation mechanism and the melting collapse mechanism due to different boundary conditions.

Oral presentation

Preliminary evaluation of the fuel debris behavior below the RPV lower head boundary of 1F Unit-2

Bando, Yamato*; Sasaki, Ryotaro*; Fukuda, Takanari*; Yamaji, Akifumi*; Yamashita, Takuya

no journal, , 

Oral presentation

Failure behavior of BWR lower head due to reaction with molten metallic materials

Sato, Takumi; Yamashita, Takuya; Shimomura, Kenta; Nagae, Yuji

no journal, , 

13 (Records 1-13 displayed on this page)
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