Zobrazeno 1 - 10
of 1 454
pro vyhledávání: '"Dry storage"'
Autor:
Seungpil Kim, Sang Soon Cho
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 10, Pp 4446-4454 (2024)
This paper presents a seismic analysis method that can evaluate a very large number of cases for the free standing dry storage cask by proposing a methodology that has short analysis time as well as accuracy. This study also performed a seismic analy
Externí odkaz:
https://doaj.org/article/0ded2af6e59c4ddcb5300d9f16c2befe
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 12, Pp 5320-5329 (2024)
CANDU spent fuels in the Wolsung site have been stored in dry storage systems, such as concrete canisters and modular air-cooled storage system. The primary role of the canister is to ensure the integrity of the fuel during the storage period, which
Externí odkaz:
https://doaj.org/article/89cd0af4bbe64ccabd2d61063515c37e
Autor:
Guo-Qiang Zeng, Shuang Qi, Peng Cheng, Sheng Lv, Fei Li, Xiao-Bo Wang, Bing-Hai Li, Qing-Ao Qin
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 8, Pp 3307-3314 (2024)
For traditional spent fuel shielding materials, due to physical and chemical defects and cost constraints, they have been unable to meet the needs. Therefore, this paper carries out the first discussion on the application and performance of bismuth i
Externí odkaz:
https://doaj.org/article/eba9a407c2304dc3ac43f77826b8a81d
Autor:
Kuat Heriyanto, Jaka Rachmadetin, Usman Sudjadi, Arbi Dimyati, Rohmad Salam, Aisyah, Pungky Ayu Artiani, Ratiko, Achmad Ramadhani, Maman Kartaman Ajiriyanto, Rosika Kriswarini, Sulistioso Giat Sukaryo, Djoko Hadi Prajitno, Abu Khalid Rivai, Daddy Setyawan
Publikováno v:
Nuclear Materials and Energy, Vol 40, Iss , Pp 101718- (2024)
Ensuring subcriticality over storage duration, even in accident condition, is one of the important requirements for dry cask designed to store spent fuel from nuclear reactor. To comply this requirement, neutron absorbers are incorporated in the spen
Externí odkaz:
https://doaj.org/article/2b444a99af4344af900194d3c2e89ce9
Publikováno v:
Scientific Reports, Vol 14, Iss 1, Pp 1-13 (2024)
Abstract Development of an effective monitoring method for spent nuclear fuel (SNF) in a dry storage cask (DSC) is important to meet the increasing demand for dry storage investigations. The DSC investigation should provide information about the quan
Externí odkaz:
https://doaj.org/article/9a606164397040e693e9febd9d74e75d
Autor:
Mirco Grosse, Felix Boldt, Michel Herm, Conrado Roessger, Juri Stuckert, Sarah Weick, Daniel Nahm
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 3, Pp 824-831 (2024)
In order to investigate the occurring processes during long-term dry storage of spent fuel assemblies, a joined project called SPIZWURZ, between the Karlsruhe Institute of Technology and the Gesellschaft für Anlagen-und Reaktorsicherheit (GRS), was
Externí odkaz:
https://doaj.org/article/966589df94094fa6b4460b7db8602ddc
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 2, Pp 728-744 (2024)
The presence of hydrogen absorbed by zirconium-based cladding materials during reactor operation can trigger degradation mechanisms and endanger the rod integrity. Ensuring the durability of the rods in extended timeframes like dry storage requires a
Externí odkaz:
https://doaj.org/article/ef0961337bfa40c3a245f7efaf8b8026
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 1, Pp 317-327 (2024)
This study investigated the chloride-induced stress corrosion cracking (CISCC) behavior expected to occur in welds of austenitic stainless steel, which are considered candidate materials for dry storage containers for spent nuclear fuel. The behavior
Externí odkaz:
https://doaj.org/article/5146310c3ed747d2ac56500ff70f5574
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 12, Pp 4597-4606 (2023)
Thermal analysis of the CANDU spent fuel dry storage canister is very important to ensure the integrity of the spent fuel. The analyses have been conducted using a conservative approach, with a particular focus on the peak cladding temperature (PCT)
Externí odkaz:
https://doaj.org/article/55c0fb4788bf494caa1a3c4eaad07635
Autor:
Dahyeon Woo, Youho Lee
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 12, Pp 4499-4513 (2022)
Spent fuel behavior of dry storage was simulated in a continuous state from steady-state operation by modifying FRAPCON-4.0 to incorporate spent fuel–specific fuel behavior models. Spent fuel behavior of a typical PWR was compared with that of NuSc
Externí odkaz:
https://doaj.org/article/ee4f861128634a36a6d2faf9680fc424