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Vega-Carrillo HR, Guadalupe Garcia-Reyna M, Angélica Marquez-Mata C, Vazquez-Bañuelos J, Eduardo Campillo-Rivera G, Bedenko SV. Effect of changing the neutron moderator in a thermal subcritical nuclear reactor. Appl Radiat Isot 2022; 188:110395. [PMID: 35939940 DOI: 10.1016/j.apradiso.2022.110395] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 05/02/2022] [Revised: 07/15/2022] [Accepted: 07/27/2022] [Indexed: 11/18/2022]
Abstract
Subcritical 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.
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Affiliation(s)
- Hector Rene Vega-Carrillo
- Unidad Academica de Estudios Nucleares de la Universidad Autonoma de Zacatecas, C. Cipres 10, Fracc, La Peñuela, 98060, Zacatecas, Zac, Mexico; Programa de Doctorado en Ingenieria y Tecnologia Aplicada, Unidad Academica de Ingenieria Electrica de la Universidad Autonoma de Zacatecas, Av. Lopez Velarde 800, Col. Centro, 98000, Zacatecas, Zac, Mexico.
| | - Mayra Guadalupe Garcia-Reyna
- Programa de Doctorado en Ingenieria y Tecnologia Aplicada, Unidad Academica de Ingenieria Electrica de la Universidad Autonoma de Zacatecas, Av. Lopez Velarde 800, Col. Centro, 98000, Zacatecas, Zac, Mexico
| | - Claudia Angélica Marquez-Mata
- TecNM/ Instituto Tecnologico de Aguascalientes, Av. Adolfo Lopez Mateos 1801 Ote. Fracc. Bona Gens, 20256, Aguascalientes, Ags, Mexico
| | - Joel Vazquez-Bañuelos
- Programa de Doctorado en Ingenieria y Tecnologia Aplicada, Unidad Academica de Ingenieria Electrica de la Universidad Autonoma de Zacatecas, Av. Lopez Velarde 800, Col. Centro, 98000, Zacatecas, Zac, Mexico
| | - Guillermo Eduardo Campillo-Rivera
- Programa de Doctorado en Ingenieria y Tecnologia Aplicada, Unidad Academica de Ingenieria Electrica de la Universidad Autonoma de Zacatecas, Av. Lopez Velarde 800, Col. Centro, 98000, Zacatecas, Zac, Mexico
| | - Sergey V Bedenko
- School of Nuclear Science and Engineering, Tomsk Polytechnic University, 634030, Tomsk, Russia
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Zarei M. An enhanced formalism for the inverse reactor kinetics problem. KERNTECHNIK 2022. [DOI: 10.1515/kern-2021-1008] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
Abstract
Abstract
The inverse kinetics problem in reactor physics is a standard formalism to unfold reactivity on the basis of registered power (flux) profile. The classical inverse point kinetics framework has been retrofitted herein to comprise thermal reactivity feedback effects. The instantaneous fuel and coolant temperatures are thus computed by way of the exponential time-differencing scheme and the corresponding thermal reactivity feedback is plugged into the inverse kinetics module. The core external reactivity is therefore unfolded employing only two consecutive time-steps of the power (flux) profile. A history independent yet straightforward numerical routine is accrued enjoying noticeable robustness with regards to the time-step resolution.
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Affiliation(s)
- Mohamad Zarei
- Engineering Department , Shahid Beheshti University , P. O. Box. 1983969411 , Tehran , Iran
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Jiang W, Zhu QF, Zhou Q, Ma F, Zhang L, Liu Y, Li JY, Ge HL, Yu R, Meng HY, Wang DW, Chen L. Reactivity worth measurement of the lead target on VENUS-II light water reactor and validation of evaluated nuclear data. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2021.108779] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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Jiang W, Gu L, Zhu QF, Zhou Q, Ma F, Zhang L, Liu Y, Li JY, Ge HL, Yu R, Meng HY, Wang DW, Dai Y, Chen L. RETRACTED: Reactivity worth measurement of the lead target on VENUS-II light water reactor and validation of evaluated nuclear data. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2020.108106] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
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Deterministic simulation of the static neutronic characteristics for the lead core of VENUS-II facility. NUCLEAR ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.nucengdes.2019.110258] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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