Fluid-fueled molten-salt reactors (MSRs) are actively being developed by several companies, with plans to deploy them internationally. The current IAEA inspection tools largely incompatible the unique design features of liquid fuel MSRs (e.g., complex chemistry, circulating inventory, bulk accountancy, and high radiation environment). For these reasons, safeguards for seen as challenging require development new techniques. This paper proposes one such technique through observation reactor’s...

The use of gradient descent methods for optimizing k-eigenvalue nuclear systems has been shown to be useful in the past, but gradients have proved computationally challenging due their stochastic nature. ADAM is a method that accounts with This analysis uses challenge problems constructed verify if suitable tool optimize systems. able successfully using despite nature and uncertainty. Furthermore, it clearly demonstrated low-compute time, high-variance estimates lead better performance...

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In this paper, we present a detailed simulation of the antineutrino emissions from an advanced gas-cooled reactor (AGR) core, benchmarked with input data United Kingdom Hartlepool reactors. An accurate description evolution spectrum cores is needed to assess performance antineutrino-based monitoring concepts for nonproliferation, including estimations sensitivity rate and fuel content thermal power. The spectral variation present, while specific AGRs, are different studies published...

Nuclear reactors have long been a favored source for antineutrino measurements estimates of power and burnup. With appropriate detector parameters background rejection, an estimate the reactor can be derived from measured event rate. Antineutrino detectors are potentially attractive as safeguards technology that monitor operations thermal distance. Advanced diverse features may present challenges current methods. By comparison, neutrino offer complementary features, including remote,...

In this article, we present the first detailed simulation of antineutrino emissions from an Advanced Gas-cooled Reactor (AGR) core, benchmarked with input data UK Hartlepool reactors. An accurate description evolution spectrum reactor cores is needed to assess performance antineutrino-based monitoring concepts for nonproliferation, including estimations sensitivity rate and fuel content thermal power. The spectral variation present, while specific AGRs, helps provide insight into likely...

Fluid fueled molten salt reactors (MSRs) are actively being developed by several companies, with plans to deploy them internationally. These have difficulties under conventional techniques (e.g., complex fuel chemistry, circulating inventory, bulk accountancy, & high radiation environment). The passive removal of certain gaseous fission products the offgas tank an MSR provides a valuable opportunity for analysis without significant modifications design system. This paper investigates that...

Nuclear reactors have long been a favored source for antineutrino measurements estimates of power and burnup. With appropriate detector parameters background rejection, an estimate the reactor can be derived from measured event rate. Antineutrino detectors are potentially attractive as safeguards technology that monitor operations thermal distance. Advanced diverse features may present challenges current methods. By comparison, neutrino offer complementary features, including remote,...

<ns5:p>Background Molten salt reactors (MSRs) can have different behavior to various types of accidents compared conventional reactors. MSRs also safety limitations that many are unfamiliar with. With limited operating time, simulations with a dynamic model valuable method analyzing the effects potential scenarios. Methods The used in this work is NERTHUS Dynamic Model MATLAB-Simulink, which generic MSR design agnostic any specific reactor design. type accident investigated pump failures...

The RBWR-TR is a thorium-based reduced moderation BWR (RBWR) with high transuranic (TRU) consumption rate. It charged LWR TRU and thorium, it recycles all actinides an unlimited number of times while discharging only fission products trace amounts through reprocessing losses. This design variant the Hitachi RBWR-TB2, which arranges its fuel in hexagonal lattice, axially segregates seed blanket regions, fits within existing ABWR pressure vessel. eliminates internal axial blanket, absorbers...

Abstract The use of gradient descent methods for optimizing k-eigenvalue nuclear system has been shown to be useful in the past, but gradients have proved challenging due their stochastic nature and uncertainty. ADAM is a method that accounts with nature. This analysis uses challenge problems constructed verify if suitable tool optimize systems. able successfully systems using despite