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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
2022 ANS Annual Meeting
June 12–16, 2022
Anaheim, CA|Anaheim Hilton
Standards Program
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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Nuclear Science and Engineering
June 2022
Nuclear Technology
Fusion Science and Technology
Latest News
What are the key cost drivers for microreactors?
Microreactors upend the traditional economics of nuclear power plants by shifting the paradigm from economies of scale (large reactors) to economies of multiple (mass production). While shrinking power output per unit may increase costs per kilowatt compared to large plants, offsetting gains can be expected from simplified and standardized designs, factory fabrication, inherent safety, lower radionuclide inventories, fast installation, and low financing costs. For instance, the lower power density in a microreactor core leads to a greatly reduced decay heat source, simplifying emergency cooling needs. These design aspects can lead to innovations including substantial simplifications to safety and control needs, minimized human operational requirements, a very compact balance of plant, the ability to fabricate almost every component in a factory, shortened construction time, and less daunting financing.
Andrew T. Bopp, Weston M. Stacey
Nuclear Technology | Volume 200 | Number 3 | December 2017 | Pages 250-268
Technical Paper | dx.doi.org/10.1080/00295450.2017.1374088
Articles are hosted by Taylor and Francis Online.
A customized dynamic safety model is developed and used to analyze the safety characteristics of the Subcritical Advanced Burner Reactor (SABR), a fast transmutation reactor driven by a tokamak fusion neutron source. Loss-of-flow accidents (LOFAs), loss–of–heat sink accidents (LOHSAs), and loss-of-power accidents (LOPAs) are analyzed taking into account the effects of feedback mechanisms, control rod insertion, and terminating electrical power to the neutron source. The core avoids fuel melting and coolant boiling without corrective action for 50% (failure of one of two pumps) loss of heat sink (LOHSA) and loss of flow (LOFA). For 100% (failure of both pumps) LOFAs, LOHSAs, and LOPAs without corrective action, coolant boiling (1156 K)/fuel melting (1473 K) occur at about 25 s/36 s, 35 s/84 s, and 25 s/36 s, respectively, after pump failure unless corrective control action is taken before this time, in which case the core power can be reduced to the decay heat level by shutting off the plasma power source. The present passive heat removal system is not sufficient to remove the decay heat, and both fuel melting and coolant boiling ultimately occur in the 100% LOFAs and LOHSAs (failure of both pumps) in either the primary or secondary system indicating the need to provide other means for decay heat removal.
