Method for determining the energy parameters in pulse reactor experiments

Vityuk, Vladimir; Vurim, Alexander

doi:10.1016/j.anucene.2018.12.013

Cited by 13 publications

(3 citation statements)

References 14 publications

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“…An IGR pulsed research reactor is a homogenous, uranium-graphite, high-temperature, self-quenching, thermal neutron reactor [14,15]. Among pulsed reactors, IGR has the highest thermal neutron fluence and integral gamma radiation dose in experimental cavity.…”

Section: Neutron Flux Source Igr Reactormentioning

confidence: 99%

Experimental Facility to Study the Threshold Characteristics of Laser Action at the p-s-Transition of Noble Gas Atom upon Excitation by 6Li(n,α)3H Nuclear Reaction Products

et al. 2022

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Almost all experimental studies of the characteristics of nuclear-excited plasma formed by excitation of gaseous media with nuclear reactions products are conducted at pulsed nuclear reactors that differ in the composition and design of the core, the duration, flux and fluence of the neutron pulse, the impulse repetition frequency, the volume and configuration of the irradiation space. This paper presents a description of the experimental (methodical and hardware) base of the National Nuclear Center of RK (Kurchatov) to conduct experiments on studying the threshold characteristics of laser action at the p-s-transition of noble gas atoms upon 6Li(n,α)3H nuclear reaction products excitation in conditions of a pulsed nuclear IGR reactor. To conduct in-pile reactor experiments, a special experimental facility was developed and constructed. The experimental facility functionally includes: in-pile experimental device, a gas–vacuum system, information and measurement system consisting of a system for registering and controlling the temperature of the device housing, and a system for registering optical radiation. The paper also briefly describes the methodology of in-pile reactor experiments on the pulsed nuclear reactor.

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Section: Neutron Flux Source Igr Reactormentioning

confidence: 99%

Experimental Facility to Study the Threshold Characteristics of Laser Action at the p-s-Transition of Noble Gas Atom upon Excitation by 6Li(n,α)3H Nuclear Reaction Products

et al. 2022

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“…An important task when testing model fuel elements and fuel assemblies in the IGR reactor is the implementation of a given power release. It, with high accuracy, is provided thanks to a number of developed methods which are aimed for the determining the tests energy parameters [5,6], location and mass of fuel composition inside the test device [7,8] and impurity gas releasing from the fuel during the irradiation [9]. IGR technical possibilities as well as the developed methodical base made it possible to launch the ambitious international experimental programs EAGLE (Experimental Acquisition of Generalized Logic to Eliminate re-criticalities) [10,11] and SAIGA (Severe Accident In-pile experiments for Gen-IV reactors and the Astrid prototype) [12].…”

Section: Introductionmentioning

confidence: 99%

Feasibility study mixed oxide fuel tests in the impulse graphite reactor

Vityuk

Vurim

et al. 2022

Eurasian j. phys. funct. mater.

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The article presents the results of computational studies to substantiate the possibility of testing the fuel of the Multipurpose hYbrid Research Reactor for a High-tech Applications reactor (MYRRHA) in the Impulse Graphite research Reactor (IGR). A scheme for conducting experiments is proposed, which allows simulating the operating conditions of MYRRHA fuel elements in a wide range of changes in their thermohydraulic parameters, including the conditions of accidents with the destruction of fuel pellets, blocking the flow area and stopping the coolant flow. A method for thermohydraulic calculations has been developed, implemented in the software environment of the computational fluid dynamics (CFD) code. A computational model of the experimental device is developed, optimized according to the spatial partitioning grid. A turbulence model for determining the parameters of convective heat and mass transfer in a eutectic lead-bismuth alloy is selected and substantiated.

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“…Currently, in the National Nuclear Center of the Republic of Kazakhstan operates two research reactors: IVG.1M [3,4] and IGR [5]. The main results of a series of reactor experiments performed on a stationary IVG.1M reactor are given in [6][7][8][9].…”

Section: Introductionmentioning

confidence: 99%

Methodology for conducting in-pile experiments to study spectral-temporal characteristic of gas media upon excitation by the 6Li(n,α)3H nuclear reaction

Samarkhanov¹,

Batyrbekov²,

Хасенов³

et al. 2022

8th International Congress on Energy Fluxes and Radiation Effects

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Almost all experimental studies of the characteristics of nuclear-excited plasma formed by the products of nuclear reactions were performed on impulse nuclear reactors, which differ in the composition and design of the core, the duration, flux and fluence of the neutron impulse, the volume and configuration of the area for irradiation, and the impulse repetition frequency. This work presents a description of the experimental (methodical and equipment) base of the National Nuclear Center of the Republic of Kazakhstan (Kurchatov) for conducting in-pile experiments at the impulse nuclear reactor IGR. The purpose of these works is to study the spectral-luminescent and spectral-temporal characteristics of optical radiation upon excitation of gas mixtures by 6Li(n,α)3H nuclear reaction products. To conduct in-pile experiments at the IGR reactor, a new experimental facility was developed. The experimental facility functionally consists of: a gas-vacuum system, an in-pile irradiation device with lithium layer, recording and temperature control systems of the device case, and an optical radiation recording system. A technique for carrying out in-pile experiments at the impulse nuclear reactor is described. To justify the design of the irradiation device and the safety analysis of conducting reactor experiments, neutron-physical and thermophysical calculations were carried out.

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Method for determining the energy parameters in pulse reactor experiments

Cited by 13 publications

References 14 publications

Experimental Facility to Study the Threshold Characteristics of Laser Action at the p-s-Transition of Noble Gas Atom upon Excitation by 6Li(n,α)3H Nuclear Reaction Products

Experimental Facility to Study the Threshold Characteristics of Laser Action at the p-s-Transition of Noble Gas Atom upon Excitation by 6Li(n,α)3H Nuclear Reaction Products

Feasibility study mixed oxide fuel tests in the impulse graphite reactor

Methodology for conducting in-pile experiments to study spectral-temporal characteristic of gas media upon excitation by the 6Li(n,α)3H nuclear reaction

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