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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
Yassin A. Hassan, Dionisie R. Moscalu
Nuclear Technology | Volume 129 | Number 1 | January 2000 | Pages 82-92
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3047
Articles are hosted by Taylor and Francis Online.
A RELAP5/MOD3.2 model of a VVER-1000 (V-320 model) nuclear power plant was updated, improved, and validated against actual power plant data. The data included steady-state and operational transient results from unit 5 of the Kozloduy nuclear power plant in Bulgaria. The first operational transient was initiated by a loss of flow at partial power conditions caused by the trip of a main coolant pump without reactor scram. The second operational transient was a continuation of the first, with the trip of a second main coolant pump.The assessment of the model has been performed in two stages: an initial validation against steady-state plant data and then a transient validation by comparison to operational transient data. The comparison between the plant data and the results of the calculations proved the adequacy of the model and demonstrated the capability of the code to reproduce the evolution of the main plant parameters.