Neutronics Model of the IVG.1M Reactor: Development and Critical-State Verification

Irkimbekov, R. A.; Zhagiparova, L. K.; Котов, В. М.; Vurim, Alexander; Gnyrya, Vyacheslav

doi:10.1007/s10512-019-00587-1

Cited by 20 publications

(12 citation statements)

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“…The IVG.1M reactor facility (Batyrbekov et al 2015, Irkimbekov et al 2019, Zhanbolatov et al 2022) is a research pressurized water reactor with the core composed of 30 water-cooled technological channels arranged in three rows along concentric circles. Each such channel contains one fuel assembly (Fig.…”

Section: The Ivg-1m Reactor Facility and Methods For Studying Its Cha...mentioning

confidence: 99%

Neutron background of composite low-enriched uranium fuel of the IVG.1M research reactor

Irkimbekov¹,

Vurim²,

Bedenko³

et al. 2022

NUCET

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IVG.1M is a research pressurized water reactor designed to use high-enriched fuel. As part of the core conversion program, the reactor will be switched to a new low-enriched composite uranium fuel. Further operation of the reactor is determined by the availability of fresh fuel to replace the core after the next campaign and the possibility of ensuring safe storage of irradiated spent nuclear fuel (SNF) unloaded from the core. The SNF storage conditions are assessed in terms of ensuring nuclear and radiation safety. Radiation safety of the research reactor fuel storage is achieved, first of all, by solving problems of protection against γ-radiation, while neutron radiation, as a rule, is not considered due to its significantly lower intensity compared to γ-radiation. As for the new low-enriched fuel of the IVG.1M reactor, which is characterized by a set of elements with low and medium atomic masses, on which the (α, n) reaction is possible, the assessment of the neutron component is a necessary procedure to ensure safe fuel storage. The authors of the article propose a procedure for calculating the neutron component of the radiation characteristics of fresh and irradiated composite fuel of the IVG.1M reactor, and also estimate the (α, n)-component. The results of the research will be useful in selecting SNF storage and transportation technologies as well as in providing scientific justification for the possibility of using neutron radiation to control burnup. The research was carried out using verified computational codes MCNP5 and Sources-4C, high-precision experimental EXFOR and computational ENDSF data, as well as evaluated nuclear data libraries.

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Section: The Ivg-1m Reactor Facility and Methods For Studying Its Cha...mentioning

confidence: 99%

Neutron background of composite low-enriched uranium fuel of the IVG.1M research reactor

Irkimbekov¹,

Vurim²,

Bedenko³

et al. 2022

NUCET

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“…At the next stage of the work, a reactor experiment was carried out with lithium CPS based on carbon fabric reinforced with CNTs. The experiment was carried out on the LIANA test bench [24,25,26,27,28] ISFNST 2021 Journal of Physics: Conference Series 2155 (2022) 012022 located at the IVG.1M reactor [29,30,31,32] hall. For the experiment, a previously developed irradiation device was used to study the materials of fusion reactors.…”

Section: Experiments On the Interaction Of Lithium Cps Based On Carbon Fabric Reinforced With Cnts With Hydrogen Isotopes Under Conditionmentioning

confidence: 99%

Tests of lithium CPS on basis of carboxylic fabric, reinforced with carbon nanotubes under high thermal and radiation loads

Tulubayev

Ponkratov

Baklanov

et al. 2022

J. Phys.: Conf. Ser.

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This work is devoted to testing a lithium CPS based on carbon fabric reinforced with carbon nanotubes under conditions of thermal and radiation loads. The paper considers and analyzes: the properties of carbon nanotubes and methods of their synthesis, the nature of the interaction of carbon materials with liquid lithium at different temperatures. A description of all the main stages in the manufacture of lithium CPS based on carbon fabric reinforced with carbon nanotubes is given. Microstructural studies of a manufactured lithium CPS sample based on carbon fabric reinforced with carbon nanotubes are presented. Studies have shown that a carbon fabric with a fiber surface reinforced with carbon nanotubes is completely wetted by liquid lithium. The developed technology is fully suitable for the manufacture of lithium CPS samples for further research. The results of experiments on the interaction of lithium CPS based on graphite fabric reinforced with carbon nanotubes with hydrogen isotopes under thermal and radiation loads are presented.

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“…В 2010 г. реактор ИВГ.1М [1,2] был включён в программу конверсии активных зон исследовательских реакторов на топливо низкого обогащения в рамках казахстанс ко американского сотрудничества, реализуемого под эгидой МАГАТЭ [3]. В феврале 2021 г. свежее низкообогащённое урановое топливо было доставлено в Нацио нальный ядерный центр Республики Казахстан (НЯЦ РК) (https://www.nnc.kz) из на учно производственного объединения «ЛУЧ» (Россия) (http://sialuch.com).…”

Section: введение введение введение введение введениеunclassified

“…2. Расчётная модель активной зоны реактора для кода MCNP5[1]: а) -3D модель активной зоны реактора ИВГ.1М; б) -поперечное сечение 3D модели (1, 2, 3 -водоохлаждаемый технологический канал первого, второго и третьего ряда; 4 -межканальные бериллиевые вытеснители; 5 -боковой бериллиевый вытеснитель)Нейтронно физическая модель реактора ИВГ.1МРасчётная модель (рис. 2) активной зоны реактора выполнена в трёхмерной поста новке с сохранением размерно массовых параметров и свойств материалов каждого элемента активной зоны реактора, указанных в проектной документации, и предназна чена для определения нейтронно физических характеристик реактора (эффективного коэффициента размножения k eff и других нейтронно физических функционалов) и нук лидного состава топлива.Расчёт нейтронно физических характеристик реактора ИВГ.1МНейтронно физические исследования и расчёт нуклидного состава топлива выпол нены по программному коду MCNP5 (Monte Carlo N Particle Transport Code System), кото рый использует библиотеки оценённых ядерных констант ENDF/BVII.0[12] для реше ния уравнений переноса частиц по объёму активной зоны.…”

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Neutron Background of Composite Low-Enriched Uranium Fuel of the IVG.1M Research Reactor

Irkimbekov

Vurim

Bedenko

et al. 2022

YadEn

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In 2010, within the framework of the Kazakhstan USA cooperation under the auspices of the IAEA, the IVG.1M reactor was included in the program for converting research reactors cores to low enriched uranium fuel.After the conversion to low enriched uranium is completed, the IVG.1M reactor operation will continue, while the duration of its operation will be determined by the availability of fresh fuel to replace the core after the next campaign and the ability to ensure safe storage of SNF removed from the core. Safe storage conditions are assessed in terms of nuclear and radiation safety.Radiation safety of storage of SNF from research reactors is primarily achieved by solving the problems of protection against γ radiation, and neutron radiation is generally not considered due to its significantly lower intensity in comparison with γ radiation. Concerning the new low enriched uranium fuel of the IVG.1M reactor, which is characterized by a set of elements with low and medium atomic mass, where the (α, n) reaction is possible, the assessment of the neutron component is a necessary procedure to ensure the safe fuel storage.The goal of this research is to estimate the neutron radiation level of fresh and irradiated fuel of the IVG.1M reactor and to develop recommendations for safe long term SNF storage.To achieve this goal, the authors of the article created a full scale computational 3D model of the reactor, carried out neutron characterization of the reactor core and studies of the evolutionary fuel composition, and calculated the neutron radiation levels of fresh and irradiated fuel.The research was carried out using verified computational codes MCNP5 and Sources 4C, high precision experimental EXFOR and computational ENDSF data, as well as evaluated nuclear data libraries.

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Neutronics Model of the IVG.1M Reactor: Development and Critical-State Verification

Cited by 20 publications

References 0 publications

Neutron background of composite low-enriched uranium fuel of the IVG.1M research reactor

Neutron background of composite low-enriched uranium fuel of the IVG.1M research reactor

Tests of lithium CPS on basis of carboxylic fabric, reinforced with carbon nanotubes under high thermal and radiation loads

Neutron Background of Composite Low-Enriched Uranium Fuel of the IVG.1M Research Reactor

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Neutronics Model of the IVG.1M Reactor: Development and Critical-State Verification

Cited by 20 publications

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﻿Neutron background of composite low-enriched uranium fuel of the IVG.1M research reactor

﻿Neutron background of composite low-enriched uranium fuel of the IVG.1M research reactor

Tests of lithium CPS on basis of carboxylic fabric, reinforced with carbon nanotubes under high thermal and radiation loads

Neutron Background of Composite Low-Enriched Uranium Fuel of the IVG.1M Research Reactor

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Neutron background of composite low-enriched uranium fuel of the IVG.1M research reactor

Neutron background of composite low-enriched uranium fuel of the IVG.1M research reactor