Influence of the Graphite’s Lifespan on the Design Value of Fuel Burnup in High Temperature Gas-Cooled Reactors; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)

Influence of the Graphite’s Lifespan on the Design Value of Fuel Burnup in High Temperature Gas-Cooled Reactors; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)

Bibliographic Details
Parent link:	Advanced Materials Research : Radiation and nuclear techniques in material science: Scientific Journal Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014).— 2015.— [P. 313-316]
Corporate Author:	Национальный исследовательский Томский политехнический университет
Other Authors:	Baybakov D. F., Golovathkiy A. V. Aleksey Vasilievich, Naymushin A. G. Artem Georgievich, Nesterov V. N. Vladimir Nikolaevich, Savanyuk S. N., Shamanin I. V. Igor Vladimirovich
Summary:	Title screen This paper describes a method of determining the correlation of the exhausted graphite fuel blocks’ lifespan in high temperature gas-cooled reactors with the fuel burnup. The axial distribution of the local values of the exhausted lifespan of graphite fuel blocks was obtained. It is shown that for ensuring the compliance of the design value of the fuel burnup with graphite fuel blocks operability, it is necessary to reduce the average mixed temperature of the helium coolant leaving the reactor core and as well as reduce the time between nuclear fuel recharges. Режим доступа: по договору с организацией-держателем ресурса
Language:	English
Published:	2015
Series:	Nuclear Engineering and Fuel Cycles
Subjects:	электронный ресурс труды учёных ТПУ графиты продолжительность жизни графитовые замедлители ядерное топливо выгорание
Online Access:	http://dx.doi.org/10.4028/www.scientific.net/AMR.1084.313
Format:	Electronic Book Chapter
KOHA link:	https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=640332

Similar Items

Determining Reactor Graphite Lifespan from Thermal Properties Degradation; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
Published: (2015)

Влияние нейтронно-физических особенностей реактора на распределение и значение эквивалентной температуры облучения графитового замедлителя; Физико-технические проблемы атомной энергетики и промышленности
Published: (2005)

Обеспечение проектного значения глубины выгорания ядерного топлива ресурсом графита топливных блоков высокотемпературных газоохлаждаемых реакторов; Известия вузов. Ядерная энергетика; № 3
Published: (2019)

Features of Fuel Burnup Calculations for Irt-T Reactor Using Mcu-Ptr Code; Journal of Industrial Pollution Control; Vol. 32, iss. 2
Published: (2016)

Experimental Simulation of the Radionuclide Behaviour in the Process of Creating Additional Safety Barriers in Solid Radioactive Waste Repositories Containing Irradiated Graphite; IOP Conference Series: Materials Science and Engineering; Vol. 142 : Innovative Technologies in Engineering
Published: (2016)

Advantages of Thorium Nuclear Fuel for Thermal-Neutron Reactors; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
by: Shamanin I. V. Igor Vladimirovich
Published: (2015)

Calculation of the Thermal State of the Graphite Moderator of the RBMK Reactor; MATEC Web of Conferences; Vol. 91 : Smart Grids 2017
Published: (2017)

Degradation of Beryllium Reflector Properties on the IRT-T Reactor; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
Published: (2015)

Facilities for Neutron Capture Therapy at IRT MEPhI Nuclear Reactor; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
Published: (2015)

Activation of Reactor Graphite Thermal Conversion Process with Copper Acetate; AIP Conference Proceedings; Vol. 2337 : Thermophysical Basis of Energy Technologies (TBET 2020)
Published: (2021)

Application of Void-Free Filling Technology for Additional Safety Barriers Creation during Uranium-Graphite Reactors Decommissioning; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
by: Izmestiev A.
Published: (2015)

Preparation of {188} W from Unenriched Targets in Middle Flux Nuclear Reactors; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
Published: (2015)

Technology for Silicon NTD Using Pool-Type Research Reactors; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
by: Varlachev V. A. Valery Aleksandrovich
Published: (2015)

Feasibility Study of Using New Fuel Composition in IRT-T Research Reactor; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
Published: (2015)

Possibility of Using Nuclear Track Membrane for Ophthalmology; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
by: Bosykh E.
Published: (2015)

Application of NANOcolloid Materials Labeled by Radionuclides in Medicine; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
Published: (2015)

Methods of Uranium Hexafluoride Purification; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
by: Orlov A. A. Aleksey Alekseevich
Published: (2015)

Effect of Hydrogen on Conductivity of Metals; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
Published: (2015)

Manifestation of the Spin in the Isotope Effects; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
Published: (2015)

Radionuclide Diagnosis of Breast Cancers; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
Published: (2015)

Use of Pulse Oximetry in Radiotherapy; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
by: Martemyanova N. I.
Published: (2015)

Way to Obtain Uranium Hexafluoride; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
by: Orlov A. A. Aleksey Alekseevich
Published: (2015)

Application of Digital Auskultometer in Radiotherapy; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
by: Aleinik A. N. Aleksandr Nikonorovich
Published: (2015)

Graphite Containing Composites Based on Bearing Steel under Boundary Sliding with High Electric Current Density; AIP Conference Proceedings; Vol. 2051 : Advanced Materials with Hierarchical Structure for New Technologies and Reliable Structures 2018 (AMHS’18)
by: Aleutdinova M. I.
Published: (2018)

Temperature Effect on the Rate of Hydrogen Desorption by Carbon Materials; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
by: Gulidova L. V. Ludmila Vladimirovna
Published: (2015)

Formation of the Irradiation Zone for Neutron Transmutation Doping Using the Pool-Type Research Reactor; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
Published: (2015)

Technology of Synthesis of Opal Matrix Metamaterials; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
Published: (2015)

UHF-Properties of Nanocomposites: Magnetic Resonance; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
Published: (2015)

Diffusion of Hydrogen in Steel by Electron Irradiation; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
Published: (2015)

Electroporation Application as an Alternative to Radiation Therapy; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
Published: (2015)

Closed Loop Identification by Optimization Method; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
by: Dyadik V. F. Valery Feodosievich
Published: (2015)

Conceptual Approach to Handling Irradiated Nuclear Fuel in Storage Systems; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
Published: (2015)

Study of hardness and tensile strength of Aluminium-7075 percentage varying reinforced with graphite and bagasse-ash composites; Resource-Efficient Technologies; Vol. 2, Iss. 2
Published: (2016)

The calculation of the campaign of reactor RITM-200; IOP Conference Series: Materials Science and Engineering; Vol. 1019 : 14th International Forum on Strategic Technology (IFOST 2019)
by: Savitsky D. E.
Published: (2021)

Modeling of Processing of Irradiated Graphite Contained Fission and Neutron-Activation Products by Noble Gas Flow; AIP Conference Proceedings; Vol. 2101 : Isotopes: Technologies, Materials and Application (ITMA-2018)
Published: (2019)

Spontaneous Radiation and Quantum Dynamics of Biological Plasma; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
Published: (2015)

Coherent Radiation of Relativistic Electrons in Dielectric Fibers; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
by: Naumenko G. A. Gennadiy Andreevich
Published: (2015)

Coherent Transition Radiation from Wire Metamaterials; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
Published: (2015)

Response of Resistant Malignant Tumors to Neutron Therapy; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
by: Musabaeva L. I.
Published: (2015)

Development of a Thermal Model of the Experimental Electrolyzer; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
by: Gladyr E. M.
Published: (2015)