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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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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.
Jae Jun Jeong, Deog Yeon Oh, Hee Cheon No, Soon Heung Chang, Sung Jae Cho, Hwang Yong Jun, Yong Kwan Lee
Nuclear Technology | Volume 90 | Number 3 | June 1990 | Pages 356-370
Technical Paper | RELAP/MOD2 / Fission Reactor | doi.org/10.13182/NT90-A34400
Articles are hosted by Taylor and Francis Online.
A compact real-time simulator for two-loop pressurized water reactor plants, FISA-2/WS (Fully Implicit Safety Analysis-2 /Work Station), has been improved and adapted to the Sun 386i computer, which was developed for classroom training in support of full-scale simulators, for transient analysis, engineering studies, and emergency drills. The FISA-2/ WS simulator package is divided into three modules: plant, on-line graphic display, and interactive communication. The plant module consists of models for core kinetics, reactor coolant system, steam generator, main steam line, and control and safety systems. Each of the models is optimized to obtain the capability of real-time simulation. Simulation results are displayed periodically at a user-specified time interval on a color monitor by the on-line graphic display module. The FISA-2/WS interactive communication module enables the user to initiate or mitigate accidents and to select one of the menu-driven graphic displays with the mouse and keyboard. Several nuclear steam supply system transients have been simulated by FISA-2/WS. The results presented here are obtained from simulations of steady state, turbine load change transient, and small-break loss-of-coolant accidents. The results of FISA-2/WS are in good agreement with plant data and the results of RELAP5/MOD2, and the fast running capability is also confirmed.