000 03396nlm1a2200493 4500
001 668429
005 20231030042148.0
035 _a(RuTPU)RU\TPU\network\39654
035 _aRU\TPU\network\39653
090 _a668429
100 _a20221130a2022 k y0engy50 ba
101 0 _aeng
102 _aNL
135 _adrcn ---uucaa
181 0 _ai
182 0 _ab
200 1 _aEffect of changing the neutron moderator in a thermal subcritical nuclear reactor
_fH. R. Vega-Carrillo, M. G. Garcia-Reyna, C. A. Marquez-Mata [et al.]
203 _aText
_celectronic
300 _aTitle screen
330 _aSubcritical thermal nuclear reactor is the combination of nuclear fuel, moderator and external neutron source. Nevertheless, the amount of neutrons increases through nuclear fissions in the 235U in the fuel, the absorption and leakage of neutrons maintain the subcriticality condition. There are several subcritical reactors with different features and purposes. The open tank subcritical reactor Nuclear Chicago model 9000 is the heterogeneous combination of natural uranium, in hexagonal lattice, and light water, acting as moderator and reflector of neutrons, that uses a239PuBe neutron source. Worldwide there are several of these reactors mainly used in education, where due to the contact with water the Al tubes have corrosion. A possible solution is to use polyethylene as moderator. Aiming to evaluate the effect of changing the moderator, in this work Monte Carlo methods were used to model the reactor with polyethylene and water as moderators increasing the fuel load. For each model were estimated the keff and the μ parameters, and for Case 10a model was calculated the power, the Ambient dose equivalent and the fluence, of neutrons and γ-rays at five sites outside the reactor.
333 _aРежим доступа: по договору с организацией-держателем ресурса
461 _tApplied Radiation and Isotopes
463 _tVol. 188
_v[110395, 8 p.]
_d2022
610 1 _aэлектронный ресурс
610 1 _aтруды учёных ТПУ
610 1 _asubcritical reactor
610 1 _anuclear chicago 9000
610 1 _aMonte Carlo
610 1 _aneutron fluence
610 1 _aambient dose equivalent
610 1 _aподкритические реакторы
610 1 _aметод Монте-Карло
610 1 _aфлюенсы
610 1 _aамбиентный эквивалент дозы
701 1 _aVega-Carrillo
_bH. R.
_gHector Rene
701 1 _aGarcia-Reyna
_bM. G.
_gMayra Guadalupe
701 1 _aMarquez-Mata
_bC. A.
_gClaudia Angelica
701 1 _aVazquez-Banuelos
_bJ.
_gJoel
701 1 _aCampillo-Rivera
_bG. E.
_gGuillermo Eduardo
701 1 _aBedenko
_bS. V.
_cphysicist
_cAssociate Professor of Tomsk Polytechnic University, Candidate of physical and mathematical sciences
_f1980-
_gSergey Vladimirovich
_2stltpush
_3(RuTPU)RU\TPU\pers\30831
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
_c20221130
_gRCR
856 4 _uhttps://doi.org/10.1016/j.apradiso.2022.110395
942 _cCF