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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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A new ANSI/ANS standard for liquid metal fire protection published
ANSI/ANS-54.8-2025, Liquid Metal Fire Protection in LMR Plants, received approval from the American National Standards Institute on September 2 and is now available for purchase.
The 2025 edition is a reinvigoration of the withdrawn ANS-54.8-1988 of the same title. The Advanced Reactor Codes and Standards Collaborative (ARCSC) identified the need for a current version of the standard via an industry survey.
Typical liquid metal reactor designs use liquid sodium as the coolant for both the primary and intermediate heat-transport systems. In addition, liquid sodium and NaK (a mixture of sodium and potassium that is liquid at room temperature) are often used in auxiliary heat-removal systems. Since these liquid metals can react readily with oxygen, water, and other compounds, special precautions must be taken in the design, construction, testing, and maintenance of the sodium/NaK systems to ensure that the potential for leakage is very small.
Harold P. Smith, Jr., Alan H. Stenning
Nuclear Science and Engineering | Volume 11 | Number 1 | September 1961 | Pages 76-84
Technical Paper | doi.org/10.13182/NSE61-A25989
Articles are hosted by Taylor and Francis Online.
The open loop dynamic performance of a nuclear rocket engine with bleed turbine or topping turbine drive is studied with the aid of an analog computer. The dynamics are accurately described by a system of ordinary, nonlinear differential equations. A linear approximation to these yield a stability criterion that is a function of (a) the rate of change of reactivity with temperature at constant propellant density, (b) the rate of change of reactivity with propellant density at constant core temperature, and (c) the relation between states of zero time rate of change of core inlet pressure. An explicit prediction of (c) is given and enables a simpler criterion to be established. The engine is stable if (a) is negative. The system is remarkably insensitive to changes of the major coefficients and can safely withstand large perturbations. It is shown that the long term response, which is dependent on the mechanical inertia of the turbopump, is of the order of ten seconds for vehicles in the million pound thrust class and that reduction of the thermal inertia of the core does not improve the response. The simulation results are explained on the basis of physical considerations and analysis in which the root locus technique proves useful.