Zobrazeno 1 - 10
of 16
pro vyhledávání: '"Tomonari Koga"'
Autor:
Tomonari Koga, Yasuhiko Tominaga
Publikováno v:
Nuclear Engineering and Design. 238:1189-1195
The present study is concerned with the characteristic cooling flow in the annular gap of a concrete cask used to store spent nuclear fuel. The concrete cask is cooled by a natural convection flow of air passing through an internal annular gap betwee
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7f3944d636d9d5387106859501526c3b
https://doi.org/10.1016/j.nucengdes.2007.03.033
https://doi.org/10.1016/j.nucengdes.2007.03.033
Publikováno v:
Journal of Nuclear Fuel Cycle and Environment. 8:145-153
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2544c77e438d904e7cc053082c38a108
https://doi.org/10.3327/jnuce.8.145
https://doi.org/10.3327/jnuce.8.145
Publikováno v:
Transactions of the Japan Society of Mechanical Engineers Series B. 76:460-462
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::295cde2de7a913b92e366cef341791ba
https://doi.org/10.1299/kikaib.76.763_460
https://doi.org/10.1299/kikaib.76.763_460
Autor:
Tomonari Koga, Osamu Watanabe
Publikováno v:
The Proceedings of the National Symposium on Power and Energy Systems. :305-310
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ead8f21e830bcfcd6571c26b365a81b3
https://doi.org/10.1299/jsmepes.2000.7.305
https://doi.org/10.1299/jsmepes.2000.7.305
Publikováno v:
Nuclear Engineering and Design. 195:57-68
Since the amount of spent fuel to be stored is expected to steadily increase in Japan, a use of large-scale dry storage facilities is considered to be a promising method in practice at reasonable economic cost. The present study is concerned with the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::239b3e2ec8697ff49e364601fc97940b
https://doi.org/10.1016/s0029-5493(99)00177-6
https://doi.org/10.1016/s0029-5493(99)00177-6
Publikováno v:
Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan. 40:966-977
Based on a prospect of steady increase in the amount of spent fuel, it is expected to establish large capacity dry storage technologies for spent fuel. This report describes the result of the heat removal test of a cask storage system using a 1/5 sca
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c7cc093c4e36b9c290fa55d78434ca20
https://doi.org/10.3327/jaesj.40.966
https://doi.org/10.3327/jaesj.40.966
Publikováno v:
Nuclear Engineering and Design. 178:295-307
This paper is devoted to logical derivation of a similarity law for single-phase natural circulation expected in a liquid metal fast reactor (LMFR). Though the way of the derivation is principally conventional, this paper shows that explicit definiti
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7d1f1f3a57797a225128cfe48936273e
https://doi.org/10.1016/s0029-5493(97)00234-3
https://doi.org/10.1016/s0029-5493(97)00234-3
Publikováno v:
Nuclear Engineering and Design. 146:25-34
A two dimensional thermal-hydraulic analysis of a natural circulation experiment has been performed to evaluate the effectiveness of a higher order finite difference method for solving the Navier-Stokes and the energy equations. In the method, the co
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::54a4d3fbaa892f269720190a944fbe62
https://doi.org/10.1016/0029-5493(94)90317-4
https://doi.org/10.1016/0029-5493(94)90317-4
Publikováno v:
Nuclear Engineering and Design. 140:331-340
This study has been conducted to establish a simulation method for the natural circulation phenomena in the reactor vessel of an LMFBR. The principal results obtained in the present study are as follows: 1. (1) Two dimensionless numbers, the Gr′ nu
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f1eaf29411dcd76baeea5812a50cda87
https://doi.org/10.1016/0029-5493(93)90116-q
https://doi.org/10.1016/0029-5493(93)90116-q
Publikováno v:
Nuclear Engineering and Design. 120:395-402
The prediction method for thermal stratification phenomena in a fast breeder reactor is described. The focus of attention is placed on the applicability of water test results to predict thermal stratification phenomena in a real plant. The basic feat
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d11fd34eb136943b0279a49ae86b5d52
https://doi.org/10.1016/0029-5493(90)90389-f
https://doi.org/10.1016/0029-5493(90)90389-f