Investigative study of the radiation damage on fuel clad of miniature neutron source reactor using computational tools
| Parent link: | Journal of Physics: Conference Series Vol. 2064 : Gas Discharge Plasmas and Their Applications (GDP 2021).— 2021.— [ 012103, 6 p.] |
|---|---|
| मुख्य लेखक: | |
| निगमित लेखक: | |
| अन्य लेखक: | , |
| सारांश: | Title screen Core conversion requires some evaluation of the reactor safety. Changes to the reactivity worth, shutdown margin, power density and material properties are crucial to the proper functioning of the reactor. The focus of this article is to study the neutron flux distribution in the reactor core and radiation damage on candidate clads. The Ghana Research Reactor-1 (GHARR-1) operates at maximum power of 30 kW in order to attain a flux of 1.0? 1012 n·cm–2·s for the high enriched uranium core. Using the GHARR-1 core geometry, considering 348 fuel pins, the multiplication factor (Keff) is calculated at enrichments of 10%, 12.5%, 16%, 20%, 30% and 90.2%. The spectrum of neutron flux generated in the 26 group is also calculated at the specified enrichments. The ion/particle interactions with the targets (clad) were studied in the Stopping and Range of Ion in Matter code to establish the best clad material based on recorded defects and vacancies generated. From the calculations and simulations, the best choice from the candidate clads based on the assessment is SiC. The calculation of the fuel campaign length gives 7.5 years. The defects sustained by the prospective clad showed low susceptibility to swelling and other forms of deformation. |
| भाषा: | अंग्रेज़ी |
| प्रकाशित: |
2021
|
| विषय: | |
| ऑनलाइन पहुंच: | http://earchive.tpu.ru/handle/11683/72799 https://doi.org/10.1088/1742-6596/2064/1/012103 |
| स्वरूप: | इलेक्ट्रोनिक पुस्तक अध्याय |
| KOHA link: | https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=667943 |
समान संसाधन
Computational neutron emission spectrometry and radiation assessment in VVER-1200 reactor nuclear fuel
प्रकाशित: (2025)
प्रकाशित: (2025)
Neutron Radiation Characteristics of the IVth GenerationReactor Spent Fuel
प्रकाशित: (2018)
प्रकाशित: (2018)
Combined source of bremsstrahlung and neutron radiation
प्रकाशित: (1998)
प्रकाशित: (1998)
Radiation effects of sic on nuclear reactors
द्वारा: Samiru Alhassan
प्रकाशित: (2021)
द्वारा: Samiru Alhassan
प्रकाशित: (2021)
Use of Thorium in Thermal-Neutron Reactors: Computation Model and Comparison of Neutronic Codes
प्रकाशित: (2016)
प्रकाशित: (2016)
Fuel Evolution in Hybrid Reactor Based on Thorium Subcritical Assembly with Open Trap as Fusion Neutron Source (Computer Simulations)
प्रकाशित: (2019)
प्रकाशित: (2019)
Core-Optimization of Ritm-200 Reactor Fuel Considering Thorium Fuel Cycle
द्वारा: Alhassan S. Samiru
प्रकाशित: (2023)
द्वारा: Alhassan S. Samiru
प्रकाशित: (2023)
Vol. C : Analysis of reactor fuel and cladding materials Vol. D : Structural analysis of reactor fuel elements and assemblies
प्रकाशित: (1981)
प्रकाशित: (1981)
Advantages of Thorium Nuclear Fuel for Thermal-Neutron Reactors
द्वारा: Shamanin I. V. Igor Vladimirovich
प्रकाशित: (2015)
द्वारा: Shamanin I. V. Igor Vladimirovich
प्रकाशित: (2015)
Computer simulation radiation damages in condensed matters
प्रकाशित: (2016)
प्रकाशित: (2016)
Prospects of the use of fast neutron reactors
द्वारा: Serikov D. A.
प्रकाशित: (2014)
द्वारा: Serikov D. A.
प्रकाशित: (2014)
Use of Thorium in Thermal-Neutron Reactors: Different Types of Fuel Compositions in VVER-1000 Reactor Cell
प्रकाशित: (2016)
प्रकाशित: (2016)
Silicon carbide coatings on zirconium alloy for light water reactor fuel cladding studies
द्वारा: Afornu B. K. Bright Kwame
प्रकाशित: (2021)
द्वारा: Afornu B. K. Bright Kwame
प्रकाशित: (2021)
Silicon carbide coatings on zirconium alloy for light water reactor fuel cladding studies
प्रकाशित: (2021)
प्रकाशित: (2021)
Gas-cooled thorium reactor at various fuel loadings and its modification by a plasma source of extra neutrons
प्रकाशित: (2019)
प्रकाशित: (2019)
Radiation damage in solids
प्रकाशित: (New York, Academic Press, 1962)
प्रकाशित: (New York, Academic Press, 1962)
Neutron data field in a fission reactor core with fusion neutron source at pulse-periodic operation
प्रकाशित: (2020)
प्रकाशित: (2020)
Subcritical assembly with thermonuclear neutron source as device for studies of neutron-physical characteristics of thorium fuel
प्रकाशित: (2016)
प्रकाशित: (2016)
Neutronic properties of high-temperature gas-cooled reactors with thorium fuel
प्रकाशित: (2018)
प्रकाशित: (2018)
On the Use of Chromium Coating for Inner-Side Fuel Cladding Protection: Thickness Identification Based on Fission Fragments Implantation and Damage Profile
द्वारा: Rofida Khamad Khlifa Khamad
प्रकाशित: (2021)
द्वारा: Rofida Khamad Khlifa Khamad
प्रकाशित: (2021)
Estimating the neutron component of radiation properties of the IVG.1M research reactor irradiated low-enriched fuel
प्रकाशित: (2022)
प्रकाशित: (2022)
Neutronic Analysis For Nuclear Reactor Systems
द्वारा: Zohuri, Bahman
प्रकाशित: (2019)
द्वारा: Zohuri, Bahman
प्रकाशित: (2019)
Neutronic Analysis For Nuclear Reactor Systems
द्वारा: Zohuri, Bahman
प्रकाशित: (2017)
द्वारा: Zohuri, Bahman
प्रकाशित: (2017)
Chromium Carbide Coatings for Inner-Side Fuel Cladding Protection: A Reactor Physics–Based Performance Analysis
द्वारा: Khlifa R. H. Rofida
प्रकाशित: (2025)
द्वारा: Khlifa R. H. Rofida
प्रकाशित: (2025)
Chromium carbide coatings for inner-side fuel cladding protection: a reactor physics - based performance analysis
द्वारा: Khlifa R. H.
प्रकाशित: (2022)
द्वारा: Khlifa R. H.
प्रकाशित: (2022)
Facility to study neutronic properties of a hybrid thorium reactor with a source of thermonuclear neutrons based on a magnetic trap
प्रकाशित: (2020)
प्रकाशित: (2020)
Neutron Sources. For Basic Physics and Applications
प्रकाशित: (Oxford, Pergamon Press, 1983)
प्रकाशित: (Oxford, Pergamon Press, 1983)
Mathematical Modelling of MNUP-Fuel Production by the Carbothermic Synthesis Process for Fast Neutron Reactors
द्वारा: Polosin A. A. Anton Alekseevich
प्रकाशित: (2018)
द्वारा: Polosin A. A. Anton Alekseevich
प्रकाशित: (2018)
Double coated cladding for advanced accident tolerant fuel - overwiew
द्वारा: Hamad Khlifa
प्रकाशित: (2022)
द्वारा: Hamad Khlifa
प्रकाशित: (2022)
Neutronic Properties Optimization Of The Irt-T Reactor Core
प्रकाशित: (2016)
प्रकाशित: (2016)
Investigating characteristics of neutrons from accelerator-driven compact source using novel target of compressed beryllium-powder
प्रकाशित: (2023)
प्रकाशित: (2023)
Neutron-physical studies of ceramic fuel of a hightemperature reactor in the regime of long-term operation
प्रकाशित: (2019)
प्रकाशित: (2019)
The organisation of the nuclear fuel cycle of the new generation based on serial thermal-neutron nuclear reactors
द्वारा: Gubaydulin I. M.
प्रकाशित: (2013)
द्वारा: Gubaydulin I. M.
प्रकाशित: (2013)
Fusion-fission hybrid reactor with a plasma source of deuterium-tritium neutrons in a linear configuration
प्रकाशित: (2022)
प्रकाशित: (2022)
Палехская миниатюра Palekh Miniature Painting
द्वारा: Некрасова М. А. Мария Александровна
प्रकाशित: (Ленинград, Художник РСФСР, 1983)
द्वारा: Некрасова М. А. Мария Александровна
प्रकाशित: (Ленинград, Художник РСФСР, 1983)
The Dosimetric Parameters Investigation of the Pulsed X-ray and Gamma Radiation Sources
द्वारा: Stuchebrov S. G. Sergey Gennadevich
प्रकाशित: (2016)
द्वारा: Stuchebrov S. G. Sergey Gennadevich
प्रकाशित: (2016)
The dosymetric parameters investigation of the pulsed gamma radiation source based on betatron
प्रकाशित: (2014)
प्रकाशित: (2014)
Tritium: Fuel of Fusion Reactors
प्रकाशित: (2017)
प्रकाशित: (2017)
Safe storage and work with neutron sources in TPU
द्वारा: Edreev S. A.
प्रकाशित: (2013)
द्वारा: Edreev S. A.
प्रकाशित: (2013)
Neutron Age Determination in Fast Reactor Materials using the Group Method
प्रकाशित: (2016)
प्रकाशित: (2016)