This work is a detailed report on the composition, operation, and findings of DANG, constructed to characterize the reactor-related radiation flux at ORNL’s HFIR in preparation for the future short baseline neutrino experiment, PROSPECT. The PROSPECT experiment aims to provide a precise measurement of the antineutrino flux and energy spectrum by taking multiple measurements 7-12 m from the core...

A collaboration between the University of Florida and the Swiss Federal Institute of Technology, Lausanne (EPFL) has been formed to develop and validate detailed coupled multiphysics models of the zero-power (100 W) CROCUS reactor at EPFL and the 100 kW University of Florida Training Reactor, for the comprehensive analysis of the reactor behavior under transient (neutronic or thermal-hydraulic ...

While the issue on Direct Containment Heating (DCH) was resolved for US reactor plants in the 1990s it was found that the consequences of DCH processes are strongly dependent on the reactor cavity configuration. Therefore, an experimental and analytical program was started in 1998 to investigate melt ejection scenarios for typical German and European reactor designs. Six experiments have been p...

Following the design of the German research reactor, FRM-II, which delivers high thermal neutron fluxes, we have already developed an asymmetric compact cylindrical core with an inner and outer reflector. The goal was to maximize the maximum thermal flux to power ratio, which is a desirable characteristic of a modern research reactor. This design, for a 10 MW power, was analyzed using MCNP, ORI...

This article demonstrates the feasibility of converting Iran’s 40MWt heavy-water research reactor at Arak (the IR-40) to use low-enriched uranium fuel in order to slow the production of weapon-usable plutonium. Two methods are proposed, and both retain identical power density, thermal-hydraulic, and safety profiles as the original design and require no physical alteration of the core. They can ...

Abstract In order to facilitate the power control method design of heat pipe nuclear reactor and avoid high complexity core modelling, paper adopts lumped parameter build thermal state dynamic model reactor. Firstly, equivalence structure transfer process “MegaPower” is carried out describe a single in hexagonal block. The complex simplified into two-zone with only fuel monolith. And equivalent...

An SPND (Self-powered Neutron Detector) is commonly used for neutron detection in NPP (Nuclear Power Plant) by virtue of un-reactivity for gamma-rays. But it has a drawback, which is that it cannot detect neutrons in real time due to beta emissions (about > 48 s) after reactions between neutrons and Rh in an SPND. And Generation IV reactors such as MSR (Molten-salt reactor), SFR (Sodium-cooled ...

A roadmap for developing accelerator driven systems (ADS) in India was prepared in 2001. The first phase of the activities under the program began with the commencement of the tenth plan in 2002. This involves the development of a 10 MeV (upgradeable to 20 MeV), 30 mA proton linear accelerator, the setting up of a lead bismuth eutectic (LBE) loop for target and coolant studies and a reactor phy...

CANDLE (Constant Axial shape of Neutron flux, nuclide number densities and power shape During Life of Energy producing reactor) reactors have been intensively researched in the last decades [1–6]. Research shows that this kind of reactor is highly economical, safe and efficiently saves resources, thus extending large scale fission nuclear energy utilization for thousands of years, benefitting t...