| مشخصات مقاله | |
| ترجمه عنوان مقاله | توسعه و کاربرد مقدماتی کد قطعی NECP-FISH برای آنالیز نوترونیکی پتوی راکتور همجوشی |
| عنوان انگلیسی مقاله | Development and preliminary application of deterministic code NECP-FISH for neutronics analysis of fusion-reactor blanket |
| انتشار | مقاله سال ۲۰۲۲ |
| تعداد صفحات مقاله انگلیسی | ۷ صفحه |
| هزینه | دانلود مقاله انگلیسی رایگان میباشد. |
| پایگاه داده | نشریه الزویر |
| نوع نگارش مقاله |
مقاله پژوهشی (Research Article) |
| مقاله بیس | این مقاله بیس میباشد |
| نمایه (index) | Scopus – Master Journals List – JCR |
| نوع مقاله | ISI |
| فرمت مقاله انگلیسی | |
| ایمپکت فاکتور(IF) |
۱٫۷۷۶ در سال ۲۰۲۰ |
| شاخص H_index | ۶۷ در سال ۲۰۲۰ |
| شاخص SJR | ۱٫۱۵۹ در سال ۲۰۲۰ |
| شناسه ISSN | ۰۳۰۶-۴۵۴۹ |
| شاخص Quartile (چارک) | Q1 در سال ۲۰۲۰ |
| فرضیه | دارد |
| مدل مفهومی | دارد |
| پرسشنامه | ندارد |
| متغیر | ندارد |
| رفرنس | دارد |
| رشته های مرتبط | مهندسی هسته ای |
| گرایش های مرتبط | راکتور، گداخت هسته ای |
| نوع ارائه مقاله |
ژورنال |
| مجله | بهداشت عمومی – Annals of Nuclear Energy |
| دانشگاه | School of Nuclear Science and Technology, Xi’an Jiaotong University, China |
| کلمات کلیدی | پتوی راکتور همجوشی، روش قطعی، آنالیز نوترونیک، NECP-FISH |
| کلمات کلیدی انگلیسی | Fusion-reactor blanket, Deterministic method, Neutronics analysis, NECP-FISH |
| شناسه دیجیتال – doi |
https://doi.org/10.1016/j.anucene.2021.108943 |
| کد محصول | E16001 |
| وضعیت ترجمه مقاله | ترجمه آماده این مقاله موجود نمیباشد. میتوانید از طریق دکمه پایین سفارش دهید. |
| دانلود رایگان مقاله | دانلود رایگان مقاله انگلیسی |
| سفارش ترجمه این مقاله | سفارش ترجمه این مقاله |
| فهرست مطالب مقاله: |
| Abstract Keywords Introduction Theory and method Framework and code development Numerical results and analysis Conclusions Declaration of Competing Interest Acknowledgments References |
| بخشی از متن مقاله: |
| Abstract The fusion-reactor blanket is very important, as it is responsible for the tritium self-sustaining, energy gain, and radiation shielding. Due to the complex structure, large geometry size and inhomogeneous neutron-flux distribution, the Monte-Carlo method is widely used for the neutronics analysis of fusion-reactor blanket, but it takes a large amount of computational time for acceptable simulation results. The deterministic code is the better choice for the fusion-reactor blanket. The geometry capability and accuracy limitation are the most important issues for the deterministic code to simulate the fusionreactor blanket. Therefore, the newly deterministic code named NECP-FISH has been developed for the fusion-reactor blanket, in which the spherical harmonic function and finite element method were applied. Moreover, the open-source platform SALOME has been applied to generate the complex geometry as pre-process of NECP-FISH. As code verification, NECP-FISH has been applied to simulate the Breeding Unit of HCCB-DEMO, using Monte-Carlo code to provide the reference results. It can be observed that the simulation results of the tritium breeding ratio (TBR), neutron flux and heat release rate provided by NECP-FISH are agreed well with corresponding values by the Monte-Carlo code. Introduction The fusion-reactor blanket is very important, as it is responsible for the tritium self-sustaining, energy gain, and radiation shielding. However, the geometry of the fusion-reactor blanket is very complicated, as there are many irregular structures applied in the blanket. Therefore, the Monte-Carlo method has been widely applied to perform the neutronics analysis of the fusion-reactor blanket, because of its advantage in powerful capability for complex geometry. As improvement in geometry modeling, the Monte-Carlo codes McCad (Große et al., 2013) and MCAM (Wu, 2009) have been updated to automatically generate the input card based on the CAD files of fusion-reactor blanket. However, large amount of particles are required for the Monte-Carlo code to simulate the fusionreactor blanket, which takes a long computational time. Therefore, the deterministic method is another choice for the modeling and simulation of the fusion-reactor blanket. |