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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
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.
Juraj Vaclav (Nuclear Regulatory Authority), Mária ?arnogurská, Tomáš Brestovi? (Technical Univ in Košice), Jaroslav Sivák (ALFA Security Technologies a.a.), Andrea Václavová (Slovak Univ of Technology in Bratislava)
Proceedings | 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017) | Charlotte, NC, April 9-13, 2017 | Pages 587-594
During transport and storage of spent nuclear fuel sub-criticality, protection of environment against radiation, and residual heat removal have to be ensured.
The paper describes the evaluation of modeling and calculation of temperature field for transport container C-30.
The aim of thermal calculations of transport container is to prove that residual heat produced by spent fuel could be safely led away without any damage to the fuel and to the container. All previous calculations considered the inventory of the container (spent fuel assemblies, cask, and water) as a homogenous entity with internal heat source.
3D model was created using ANSYS CFX software. It models in a simply way fuel assemblies as well as a cooling medium flow.
Each spent fuel assembly is divided into two parts. The central circular part represents the area of water between fuel pins. This part does not produce any heat. The rest of the assembly is bordered by hexagon on the outer periphery and by a circle inside of the fuel assembly. Only this part is responsible for heat production.
The calculations were made for residual heat output of 5, 10, 15, 20 and 24 kW.
The results were compared with experimentally obtained values.