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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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.
Jianhang Zhou, Jinglong Zhang, Jie Zhang, Yipo Zhang, Hong Yang
Fusion Science and Technology | Volume 78 | Number 7 | October 2022 | Pages 588-594
Technical Note | doi.org/10.1080/15361055.2022.2090785
Articles are hosted by Taylor and Francis Online.
Neutron flux measurement provides essential data for the diagnostic tools that control plasma combustion, equipment maintenance, and radiation safety and reveals key information on plasma physics, machine protection, and control issues. To obtain rapid change of the neutron emission rate by magnetohydrodynamic instabilities, a fast neutron flux measurement system with high time resolution (~10 ) was developed on the HL-2M tokamak (located at Southwestern Institute of Physics, China). The system includes four EJ-410 detectors and four digitizers that we developed ourselves with dedicated field-programmable gate array firmware, including a waveform recording function, real-time count rate measurement, and real-time integration measurement. The simulation results show that the throughput rate of the readout electronics is 96.7% when the input counting rate is 1 mega count per second (Mcps) and the throughput rate could achieve 63.8% when the input counting rate is 6 Mcps. Moreover, when the input counting rate increases further to 10 Mcps, the integration model may be used. Given that this measurement system is highly portable and has a high time resolution, it is suitable for the fast neutron flux diagnostic on the HL-2A tokamak.