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This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Sergei A. Zimin
Fusion Science and Technology | Volume 20 | Number 2 | September 1991 | Pages 144-163
Technical Paper | Shielding | doi.org/10.13182/FST91-A29686
Articles are hosted by Taylor and Francis Online.
The radiation shield for the toroidal field (TF) coils in the International Thermonuclear Experimental Reactor (ITER) is optimized using one-dimensional calculations. The ANISN code with the VITAMIN-C group constant library and MAKLIB-IV response library are used for the calculations. Two ways of evaluating the total heating in the TF coils are presented. These methods, being standard approaches, use the results of both one-dimensional shielding calculations and three-dimensional calculations f or the neutron wall load distribution on the reactor first wall, and they seem to be useful f or future work on ITER and ITER-like projects such as the Next European Torus (NET), Fusion Experimental Reactor (FER), and Compact Ignition Tokamak (CIT). The main results of the optimization and the total heating evaluation are compared with U.S. and European team results. The local nuclear responses in the TF coils remain within the prescribed limits everywhere. The total nuclear heating in the ITER TF coils is within the 50-kW limit in the physics phase using either the U.S. or the USSR blanket concept. The total nuclear heating in the ITER TF coils during the technology phase is expected to be ∼20% lower than that in the physics phase.