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182		0	_ab
200	1		_aInvestigative study of the radiation damage on fuel clad of miniature neutron source reactor using computational tools _fS. Alkhassan, S. V. Belyavsky, V. N. Nesterov
203			_aText _celectronic
300			_aTitle screen
320			_a[References: 9 tit.]
330			_aCore 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.
461		0	_0(RuTPU)RU\TPU\network\3526 _tJournal of Physics: Conference Series
463			_tVol. 2064 : Gas Discharge Plasmas and Their Applications (GDP 2021) _o15th International Conference, 5-10 September 2021, Ekaterinburg, Russia _v[ 012103, 6 p.] _d2021
610	1		_aэлектронный ресурс
610	1		_aтруды учёных ТПУ
700		1	_aAlkhassan _bS. _gSamiru
701		1	_aBelyavsky _bS. V. _gSergey Vladimirovich
701		1	_aNesterov _bV. N. _cspecialist in the field of nuclear energy _cassociate Professor of Tomsk Polytechnic University, candidate of technical Sciences _f1977- _gVladimir Nikolaevich _2stltpush _3(RuTPU)RU\TPU\pers\35579
712	0	2	_aНациональный исследовательский Томский политехнический университет _bИнженерная школа ядерных технологий _bОтделение ядерно-топливного цикла _h7864 _2stltpush _3(RuTPU)RU\TPU\col\23554
801		2	_aRU _b63413507 _c20220830 _gRCR
856	4		_uhttp://earchive.tpu.ru/handle/11683/72799
856	4		_uhttps://doi.org/10.1088/1742-6596/2064/1/012103
942			_cCF