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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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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.
M. P. Paulsen, B. E. Griebenow, L. R. Feinauer, J. H. McFadden, Peter J. Jensen
Nuclear Technology | Volume 83 | Number 3 | December 1988 | Pages 274-288
Technical Paper | Fifth International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34141
Articles are hosted by Taylor and Francis Online.
The RETRAN-02 transient thermal-hydraulic analysis program has found wide acceptance by the nuclear utility industry for performing analyses of operational transients and small-break loss-of-coolant accidents. There are, however, known limitations with RETRAN-02 and the Electric Power Research Institute has sponsored the development of RETRAN-03 to address these limitations. The major objectives of the development program are (a) to extend the range of analyses that can be performed with RETRAN, (b) to make the code more dependable and faster running, and (c) to have a more transportable code. Summaries of the RETRAN-02 models that have been modified for RETRAN-03, new models that have been added, and the new semi-implicit steady-state and dynamic solution methods are presented. The primary development task associated with improving the transportability of the code dealt with implementing the IBM and CDC environmental libraries (assembly language) using a common FORTRAN 77 source. The salient results of this work are discussed.