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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
Standards Program
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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Ho Nieh nominated to the NRC
Nieh
President Trump recently nominated Ho Nieh for the role of commissioner in the Nuclear Regulatory Commission through the remainder of a term that will expire June 30, 2029.
Nieh has been the vice president of regulatory affairs at Southern Nuclear since 2021, though he is currently working as a loaned executive at the Institute of Nuclear Power Operations, where he has been for more than a year.
Nieh’s experience: Nieh started his career at the Knolls Atomic Power Laboratory, where he worked primarily as a nuclear plant engineer and contributed as a civilian instructor in the U.S. Navy’s Nuclear Power Program.
From there, he joined the NRC in 1997 as a project engineer. In more than 19 years of service at the organization, he served in a variety of key leadership roles, including division director of Reactor Projects, division director of Inspection and Regional Support, and director of the Office of Nuclear Reactor Regulation.
Dieter Althaus, Nicolas Brahy
Nuclear Technology | Volume 78 | Number 3 | September 1987 | Pages 284-294
Nuclear Power Plant Kalkar (SNR-300) | Fission Reactor | doi.org/10.13182/NT87-A15994
Articles are hosted by Taylor and Francis Online.
Handling equipment is installed at the rotating shield plug of the reactor vessel after a shutdown for refueling or for replacing of defective fuel subassemblies. Core subassemblies are unloaded (after a short decay time) inside sodium-filled cans by means of a shielded gas-cooled flask and are placed in a sodium-cooled storage vessel for activity decay. To locate a fuel pin defect in the core, suspicious fuel subassemblies are extracted from the core and leak tested above the core using the in-vessel handling machine. Handling machines are developed from corresponding KNKII equipment supported by prototype tests performed in an Interatom sodium test facility. Handling of core subassemblies and of other radioactive components outside the reactor vessel is done by a multipurpose transfer machine. The sodium-cooled fuel storage has a capacity of one core loading of fuel subassemblies. Handling operations are remotely controlled. Provisions are made for an outer dimensional control of fuel subassemblies in the course of a refueling shutdown. The preoperational tests under sodium are completed, and some of the reflector subassemblies have been loaded into the core under sodium. These tests and operations have shown reliable equipment performance.