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Journal Articles

Validation of three-dimensional finite-volume-particle method for simulation of liquid-liquid mixing flow behavior

Kato, Masatsugu*; Funakoshi, Kanji*; Liu, X.*; Matsumoto, Tatsuya*; Liu, W.*; Morita, Koji*; Kamiyama, Kenji

Proceedings of 11th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-11) (Internet), 7 Pages, 2018/11

JAEA Reports

Case studies of radiation dose assessment in emergency situation of nuclear facilities

Kawasaki, Masatsugu; Nakajima, Junya; Yoshida, Keisuke; Kato, Saori; Nishino, Sho; Nozaki, Teo; Nakagawa, Masahiro; Tsunoda, Junichi; Sugaya, Yuki; Hasegawa, Rie; et al.

JAEA-Data/Code 2017-004, 57 Pages, 2017/03

JAEA-Data-Code-2017-004.pdf:2.34MB

In emergency situation of nuclear facilities, we need to estimate the radiation dose due to radiation and radioactivity to grasp the influence range of the accident in the early stage. Therefore, we prepare the case studies of dose assessment for public exposure dose and personal exposure dose and contribute them to emergency procedures. This document covers about accidents of nuclear facilities in Nuclear Science Research Institute and past accident of nuclear power plant, and it can be used for inheritance of techniques of emergency dose assessment.

Oral presentation

Particle-based simulation of fluid behavior in two-component mixture pool

Yamauchi, Toshiya*; Ogawa, Ryusei*; Kato, Masatsugu*; Liu, X.*; Matsumoto, Tatsuya*; Morita, Koji*; Kamiyama, Kenji; Suzuki, Toru

no journal, , 

no abstracts in English

Oral presentation

Validation of particle-based simulation for two-liquid mixed flow behavior

Ogawa, Ryusei*; Yamauchi, Toshiya*; Kato, Masatsugu*; Liu, X.*; Matsumoto, Tatsuya*; Morita, Koji*; Kamiyama, Kenji; Suzuki, Toru

no journal, , 

no abstracts in English

Oral presentation

Validation of three-dimensional finite volume particle method for simulation of two-liquid mixture flow behavior

Kato, Masatsugu*; Ogawa, Ryusei*; Funakoshi, Kanji*; Liu, X.*; Matsumoto, Tatsuya*; Liu, W.*; Morita, Koji*; Kamiyama, Kenji

no journal, , 

no abstracts in English

Oral presentation

Three-dimensional particle-based simulation of heat transfer behavior from molten mixture pool to structural wall

Funakoshi, Kanji*; Kato, Masatsugu*; Liu, X.*; Liu, W.*; Morita, Koji*; Kamiyama, Kenji

no journal, , 

In order to eliminate the energetic potential in the case of postulated core-disruptive accidents (CDAs) of sodium-cooled fast reactors, introduction of a fuel subassembly with an inner-duct structure (FAIDUS) has been proposed. In the present study, to demonstrate a function for early fuel discharge, analytical study using three-dimensional particle-based simulations were performed against a series of multi-component, multi-phase thermal hydraulics phenomena, which are formation of molten pool of fuel and steel mixture caused by disruption of fuel pins, and, heat-transfer from the pool to duct wall.

Oral presentation

3D particle-based simulation of molten pool-to-duct wall heat transfer in EAGLE ID1 in-pile test

Sakaguchi, Kazuya*; Funakoshi, Kanji*; Kato, Masatsugu*; Liu, X.*; Liu, W.*; Morita, Koji*; Kamiyama, Kenji

no journal, , 

no abstracts in English

Oral presentation

3D particle-based simulation of molten pool-to-duct wall heat transfer in EAGLE ID1 in-pile test

Sakaguchi, Kazuya*; Funakoshi, Kanji*; Kato, Masatsugu*; Liu, X.*; Liu, W.*; Morita, Koji*; Kamiyama, Kenji

no journal, , 

no abstracts in English

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