Zobrazeno 1 - 10
of 20
pro vyhledávání: '"Masumi Wataru"'
Publikováno v:
Basics of Transport and Storage of Radioactive Materials
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::de852653fbbb57da1b1743683da62b9a
https://doi.org/10.1142/9789813234048_0022
https://doi.org/10.1142/9789813234048_0022
Publikováno v:
Basics of Transport and Storage of Radioactive Materials
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2d51cccfaf3a766e5a0138e3adb99c85
https://doi.org/10.1142/9789813234048_0004
https://doi.org/10.1142/9789813234048_0004
Autor:
Toshiari Saegusa, Masumi Wataru
Publikováno v:
Journal of the Atomic Energy Society of Japan. 57:259-264
Autor:
Toshiari Saegusa, Koji Shirai, Akihiro Sasahara, T. Arai, Masumi Wataru, Junichi Tani, Hirofumi Takeda, P. L. Winston
Publikováno v:
Nuclear Engineering and Technology. 42:237-248
The safety of metal cask and concrete cask storage technology has been verified by CRIEPI through several research programs on demonstrative testing for the interim storage of spent fuel. The results have been reflected in the safety requirements for
Publikováno v:
Nuclear Engineering and Design. 238:1196-1205
Heat removal tests using two types of full-scale concrete casks were conducted. This paper describes the results under a normal condition of spent fuel storage. In the tests, data on heat removal performance and integrity of cask components were obta
Publikováno v:
Nuclear Engineering and Design. 238:1206-1212
Heat removal verification tests using two kinds of full-scale concrete casks under accident conditions were performed. One is reinforced concrete cask and the other is concrete filled steel cask. From the test results, their safety on heat removal pe
Publikováno v:
Nuclear Engineering and Design. 238:1220-1226
In the concrete cask storage system, spent fuel is installed and weld-sealed in a cylindrical container called a canister. The canister is filled with helium gas and its containment shall be maintained and inspected during storage. The helium gas enh
Publikováno v:
Nuclear Engineering and Design. 238:1213-1219
To develop a thermal analysis method for the concrete cask, numerical calculation based on thermal hydraulic phenomena was performed. In the present calculation model, calculation area was divided into two parts. One is inside of the canister and the
This chapter introduces the amount of spent fuel generation and storage in the world and the characteristics of spent fuel. An overview of the historical development of spent fuel storage technologies is provided and some examples of the storage cask
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f2be27dc86534a3928bbe34235f71a1e
https://doi.org/10.1016/b978-1-78242-309-6.00014-9
https://doi.org/10.1016/b978-1-78242-309-6.00014-9
Publikováno v:
Journal of Nuclear Fuel Cycle and Environment. 8:145-153