The PGR pulsed graphite reactor

Kurchatov, I.V.; Feinberg, Samuel M.; Dollezhal, N. A.; Aleshchenkov, P. I.; Drozdov, F. S.; Emel'yanov, I. Ya.; Жирнов, А. Д.; Kazachenko, M. A.; Knyazeva, G. D.; Kondrat'ev, F. V.; Lavrenikov, V.D.; Morgunov, N. G.; Petunin, B.V.; Smirnov, V. P.; Talyzin, V. M.; Filippov, A. G.; Chikhladze, I. L.; Chulkov, P. M.; Shevelev, Ya.V.

doi:10.1007/bf01122769

Cited by 14 publications

(5 citation statements)

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“…For this purpose, experiments are carried out both in reactor and non-reactor installations. For example, thanks to the design features of the research impulse graphite reactor IGR [1], it is possible to conduct large-scale experiments with a model fuel assembly containing up to 10 kg of uranium dioxide [2]. There is a need to transport nuclear materials to the assembly site of model fuel assemblies to conduct experiments on time.…”

Section: Introductionmentioning

confidence: 99%

Safety Justification for Transportation of Nuclear Materials

Kelsingazina

2024

jour

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The Institute of Atomic Energy of the National Nuclear Center of the Republic of Kazakhstan conducts a large number of studies to justify the safety of designed reactors and already operating reactors. Experiments are carried out both at in-pile and out-of-pile research installations. To implement these studies, there is a need to transport nuclear materials to the place where they are performed. Thus, it is necessary to justify the safety of nuclear material transportation. This paper presents neutronic calculations of the effective neutron multiplication factor to justify the safety of nuclear material transportation in accordance with the legislation of the Republic of Kazakhstan. The calculations used the most commonly transported type of nuclear materials – uranium dioxide (UO2) fuel pellets of various enrichments. Transportation was conducted using a transport packaging set IP-1, in accordance with the rules for the transportation of nuclear materials. Both normal and emergency conditions for the transportation of nuclear materials were modeled, taking into account the possibility of water leaking into the packaging and water getting into canisters with uranium dioxide fuel pellets. To determine the effective neutron multiplication factor (keff) of the transport and packaging set, the Monte Carlo calculation method was used in the MCNP5 program, with the ENDF/B-VII nuclear data library.

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Section: Introductionmentioning

confidence: 99%

Safety Justification for Transportation of Nuclear Materials

Kelsingazina

2024

jour

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“…The National Nuclear Center of the Republic of Kazakhstan (NNC RK), operating the IGR reactor, has significant experience in such studies [4]. The technical characteristics of the IGR make it possible to carry out in-reactor research aimed at obtaining information about the processes occurring in the elements of nuclear reactors in transient and emergency modes.…”

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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“…1 on different scales but with an indication of at least one characteristic dimension. Some structural features are not shown but they are presented in the primary sources [6][7][8][9][10][11][12][13][14][15][16][17][18][19][20][21]. The fuel elements and assemblies with the simplest shapes, for example, F-1, CP-1, X-10, and EBR I rods, are not shown.…”

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confidence: 96%

“…They are not like any of the fuel elements or assemblies of any other reactor; it is impossible to confuse them with anything. The material of the TREAT block is similar to the fuel block of the Soviet (now Kazakhstan) IGR reactor [20] (see Fig. 1, position h) but the dimension and structural features are different; for example, the angles of the TREAT block are truncated, the IGR block has an axial opening, TREAT has a hermetic shell, while IGR does not.…”

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confidence: 99%

Possibility of identifying the fuel elements and fuel assemblies of first-generation USA and USSR research reactors

et al. 2013

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The possibilities of identifying the fuel elements and fuel assemblies from the cores of first-generation research reactors in the USSR (F1, TVR, RFT, IGR, and IVG.1) and USA BGRR, EBR I, MTR, ARE, and TREAT) are examined. The fuel elements and assemblies are described and the cross section and characteristic dimensions are presented. It is shown that the fuel elements and fuel assemblies are different and that in order to identify them in most cases only the geometric dimensions need by examined and measured. However, if a reactor fuel element or assembly is completely destroyed, then the uranium enrichment and isotopic composition as well as the impurity composition must be measured.In recent years, there have been cases of trafficking in nuclear materials [1]. In 2005, there were 101 cases of unauthorized activity involving nuclear and radioactive materials -18 cases involved nuclear, 76 radioactive, and 7 radioactively contaminated materials [2]. From the standpoint of the threat from terrorism, the rare cases involving radioactive materials are not of great concern but the actions taken against trafficking should not depend on the number of events that have occurred, since the consequences of even a single unlawful use such material can be serious.Since 1942, approximately 660 research reactors have been built, including about 250 in the US, and more than 100 research reactors and critical assemblies were operated in the USSR. Their fuel can attract wrongdoers because it is often fabricated from high-enrichment uranium. When nuclear material of unknown origin is detained, it must be identified in order to determine the sites of production, operation, misappropriation and suppression of subsequent illegal acts. Countermeasures against trafficking of nuclear materials, and in particular identification, are topical matters, in connection with which the term

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The PGR pulsed graphite reactor

Cited by 14 publications

References 1 publication

Safety Justification for Transportation of Nuclear Materials

Safety Justification for Transportation of Nuclear Materials

Feasibility study mixed oxide fuel tests in the impulse graphite reactor

Possibility of identifying the fuel elements and fuel assemblies of first-generation USA and USSR research reactors

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