ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
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.
Takuro Honda, Takashi Okazaki, Yasushi Seki, Isao Aoki, Tomoaki Kunugi
Fusion Science and Technology | Volume 30 | Number 1 | September 1996 | Pages 95-103
Technical Paper | Safety and Environmental Aspect | doi.org/10.13182/FST96-A30766
Articles are hosted by Taylor and Francis Online.
Dust production due to plasma disruptions has been investigated using a safety analysis code, which can calculate the plasma dynamics and thermal characteristics of fusion reactor structures simultaneously. We selected two fusion reactor designs in the International Thermonuclear Experimental Reactor (ITER), i.e., the Engineering Design Activity (EDA) and the Conceptual Design Activity (CDA). The ITER/EDA will adopt beryllium for the plasma-facing component (PFC), and the ITER/CDA adopted graphite for PFC. The beryllium dust production in the ITER/EDA reactor will range from 7.0 to 10.3 kg/disruption, which strongly depends on vapor shield effects. The carbon dust production in the ITER/CDA reactor will range from 1.9 to 2.4 kg/disruption. However, the carbon dust will increase by as much as a factor of 2 to 5 because the effective latent heat of graphite has a large uncertainty under the extremely high heat flux during disruptions. For both, dust production from the first wall depends on the current quench time during disruptions. If the current quench time can be extended, the beryllium dust from the first wall will be minimized, and the carbon dust from there will be negligible.