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Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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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Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Kåre Hannerz, Lars Nilsson, Tor Pedersen, Christen Pind
Nuclear Technology | Volume 91 | Number 1 | July 1990 | Pages 81-88
Technical Paper | Safety of Next Generation Power Reactor / Nuclear Safety | doi.org/10.13182/NT90-A34443
Articles are hosted by Taylor and Francis Online.
The process inherent ultimate safety (PIUS) reactor is a 600-MW(electric) pressurized water reactor based on a concept developed and verified at ABB Atom during the last 10 years. It is designed to eliminate any possibility of a core degradation accident. Its basic design features a core that is openly connected, in a natural-circulation circuit, to a large pool of heavily borated water. This pool is kept in place by a prestressed concrete pressure vessel provided with redundant leakage barriers. The coolant pumps are operated so that there is hydraulic balance in the openings between the primary coolant loop and the pool. Therefore, the hot, low-boron primary loop water is kept separated from the pool water in spite of the always open natural-circulation path. In severe transients, such as loss of feedwater, this balance is affected, and pool water ingress occurs. Reactor shutdown and long-term residual heat removal are ensured without monitoring and intervention. Thus, safety is independent of potentially failure-prone devices and cannot be jeopardized by mistakes or malicious human acts. During normal operation, boron ingress to the primary loop due to turbulent diffusion can be kept at an adequately low level, as shown by a series of investigations and experiments. In transients the thermally stratified layer that separates hot primary coolant from cold high-boron pool water moves vertically. Large movements result in boron ingress and operational disturbances. These movements can be reliably calculated by computer simulations, as confirmed by test loop operation. Simulations and tests have shown that PIUS can survive even a grid voltage disturbance, implying loss-of-coolant pump power supply for >0.5 s, without boron ingress to the primary loop. (This severe operational transient is a Scandinavian requirement.) Hence, the risk that PIUS will experience spurious shutdowns due to the special arrangement for prevention of core degradation accidents is very small. The arrangement instead provides for plant simplification because of fewer safety systems and improved operator comprehension. PIUS should become a user friendly plant that can be run with high availability and for a long plant life.