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Latest News
Oklo signs MOU to partner with Korea Hydro & Nuclear Power
Oklo cofounder and CEO Jacob DeWitte and KHNP CEO Joo-ho Whang following the virtual signing of an MOU. (Source: Oklo)
Oklo announced last week that it hopes to expand development and global deployment of its advanced nuclear technology through a new partnership with Korea Hydro & Nuclear Power.
The memorandum of understanding includes plans for the companies to advance standard design development and global deployment of Oklo’s planned Aurora Powerhouse, a microreactor that would generate 15 MW and be scalable to 50 MWe. Oklo said each unit can operate for 10 years or longer before refueling.
Oklo and KHNP plan to cooperate on early-stage project development, including manufacturability assessments and planning of major equipment, supply chain development for balance-of-plant systems, and constructability assessments and planning.
E. A. Mogahed
Fusion Science and Technology | Volume 44 | Number 1 | July 2003 | Pages 69-73
Technical Paper | Fusion Energy - MFE Chamber Technology | doi.org/10.13182/FST03-A312
Articles are hosted by Taylor and Francis Online.
A helical coolant channel scheme is proposed for the APEX solid wall blanket module. The self-coolant breeder in this system is FLIBE (LiF)2(BeF2). The structural material is the nanocomposited alloy 12YWT. The neutron multiplier used in the current design is either stationary or slow moving liquid lead. The purpose of this study is to design a blanket that can handle a high wall loading (5 MW/m2). In the mean time the design provides means to attain the maximum possible blanket outlet temperature and meet all engineering limits on temperature of structural material and liquids. An important issue for such a design is to optimize the system for minimum pressure loss. For advanced ferritic steel (12YWT) an upper temperature limit of 800°C is expected, and a limit of 700°C at the steel/FLIBE interface is recommended.The blanket module is composed of two main continuous routes. The first route is three helical rectangular channels side-by-side that surround a central box. The helical channels are fed from the bottom and exit at the top to feed the central channels in the central box. The coolant helical channels have a cross sectional area with a length of about 10 cm and a width that changes according to the position around the central box. For instance: the width of the coolant channels facing the plasma is the narrowest while it is the widest in the back (farthest from the plasma).In this design the coolant runs around the central box for only 5 turns to cover the total height of the first wall (6.8 m). The design is optimized with the FW channel width as a parameter with the heat transfer requirements at the first wall as the constraints.