Diego Medina-Castro , Hector Rene Vega-Carrillo , Antonio Baltazar-Raigosa , Tzinnia Gabriela Soto-Bernal , Régulo López-Callejas , Benjamín Gonzalo Rodríguez-Méndez
{"title":"Monte Carlo analysis of nitrided Al-6061-T6 as an alternative fuel holder tube in subcritical reactors","authors":"Diego Medina-Castro , Hector Rene Vega-Carrillo , Antonio Baltazar-Raigosa , Tzinnia Gabriela Soto-Bernal , Régulo López-Callejas , Benjamín Gonzalo Rodríguez-Méndez","doi":"10.1016/j.net.2025.103775","DOIUrl":null,"url":null,"abstract":"<div><div>The selection of fuel holder tube material in subcritical reactors is critical for operational safety and long-term efficiency. In this study, a Monte Carlo analysis using the MCNP5 code was conducted to evaluate the impact of replacing Al-6061-T6 with its nitrided variant (Al-6061-T6-N), treated via Plasma Immersion Ion Implantation (PIII), as a structural material for the fuel holder tubes in a low-power subcritical reactor. The results showed that the surface modification does not induce significant changes in the effective multiplication factor or in the neutron and gamma-ray spectra. Likewise, the Ambient dose equivalents measured at various positions around the reactor remained virtually unchanged. These findings suggest that the PIII technique preserves the essential nuclear interaction properties of the material without compromising radiological safety. However, complementary experimental studies are recommended to validate its long-term performance under real operating conditions and radiation-induced aging.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103775"},"PeriodicalIF":2.6000,"publicationDate":"2025-06-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Technology","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S1738573325003432","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
The selection of fuel holder tube material in subcritical reactors is critical for operational safety and long-term efficiency. In this study, a Monte Carlo analysis using the MCNP5 code was conducted to evaluate the impact of replacing Al-6061-T6 with its nitrided variant (Al-6061-T6-N), treated via Plasma Immersion Ion Implantation (PIII), as a structural material for the fuel holder tubes in a low-power subcritical reactor. The results showed that the surface modification does not induce significant changes in the effective multiplication factor or in the neutron and gamma-ray spectra. Likewise, the Ambient dose equivalents measured at various positions around the reactor remained virtually unchanged. These findings suggest that the PIII technique preserves the essential nuclear interaction properties of the material without compromising radiological safety. However, complementary experimental studies are recommended to validate its long-term performance under real operating conditions and radiation-induced aging.
期刊介绍:
Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters.
NET covers all fields for peaceful utilization of nuclear energy and radiation as follows:
1) Reactor Physics
2) Thermal Hydraulics
3) Nuclear Safety
4) Nuclear I&C
5) Nuclear Physics, Fusion, and Laser Technology
6) Nuclear Fuel Cycle and Radioactive Waste Management
7) Nuclear Fuel and Reactor Materials
8) Radiation Application
9) Radiation Protection
10) Nuclear Structural Analysis and Plant Management & Maintenance
11) Nuclear Policy, Economics, and Human Resource Development