Thermal-Hydraulic and Neutronic Design for a Super Critical Water Reactor Using Nanofluid as Coolant

سال انتشار: 1403
نوع سند: مقاله ژورنالی
زبان: انگلیسی
مشاهده: 24

فایل این مقاله در 16 صفحه با فرمت PDF قابل دریافت می باشد

استخراج به نرم افزارهای پژوهشی:

لینک ثابت به این مقاله:

شناسه ملی سند علمی:

JR_IJCCE-43-8_015

تاریخ نمایه سازی: 17 خرداد 1404

چکیده مقاله:

The most important intrinsic limitation of conventional coolant fluids is their relatively low thermal conductivity. In this regard, in the last two decades, by introducing a new concept called nanofluid, researchers have improved the thermal conductivity of conventional coolants; furthermore, thermal efficiency, as well as convection heat transfer of the thermal-hydraulic cycles, is increased by applying coolants at supercritical pressures. A supercritical water reactor is one of the generation IV reactors, which is a creative mixture of conventional pressurized water reactors and supercritical pressure steam boilers. In the present study, by applying the concept of nanofluid coolants in a typical supercritical pressure water reactor, the thermo-neutronic behavior of the reactor core was investigated. In this manner, thermodynamic properties of the applied coolant were evaluated by adding numerical models of nanofluid properties to the IAPWS-IF۹۷, and for simulation of the thermal-hydraulic behavior of the coolant, a modular computer code has been developed using the C# programming language based on the porous media approach, and neutronic simulation was performed by the MCNP code. Final results showed that application of a water-based Al۲O۳ nanofluid with ~۱۱% mass fraction (~۲% volume fraction at the core inlet) as coolant without any violation of neutronic characteristics of the core is achievable and the criticality of the core would be sustained. Calculations indicate that applying nanofluids to the core will flatten the radial neutron flux in the reactor core, and the convection heat transfer coefficient will improve by ۲%.

کلیدواژه ها:

Supercritical Water Reactors ، Thermal-hydraulic and Neutronic Analysis ، nanofluid ، MCNP code ، C# programming language

نویسندگان

Homa Takhshid

Department of Nuclear Engineering, Science and Research Branch, Islamic Azad University, Tehran, I.R. IRAN

Gholamreza Jahanfarnia

Department of Nuclear Engineering, Science and Research Branch, Islamic Azad University, Tehran, I.R. IRAN

Mohsen Kheradmand Saadi

Department of Nuclear Engineering, Science and Research Branch, Islamic Azad University, Tehran, I.R. IRAN

Mohammad Hossein Rahimi

Department of Nuclear Engineering, Science and Research Branch, Islamic Azad University, Tehran, I.R. IRAN

مراجع و منابع این مقاله:

لیست زیر مراجع و منابع استفاده شده در این مقاله را نمایش می دهد. این مراجع به صورت کاملا ماشینی و بر اساس هوش مصنوعی استخراج شده اند و لذا ممکن است دارای اشکالاتی باشند که به مرور زمان دقت استخراج این محتوا افزایش می یابد. مراجعی که مقالات مربوط به آنها در سیویلیکا نمایه شده و پیدا شده اند، به خود مقاله لینک شده اند :
  • Schulenberg T., Starflinger J., High Performance Light Water Reactor (Design ...
  • Oka Y., Koshizuka S., Yamasaki T., Direct Cycle Light Water ...
  • Okano Y., Koshizuka S., Oka Y., Design of Water Rod ...
  • Dobashi K., Oka Y., Koshizuka S., Core and Plant Design ...
  • Hofmeister J., Waata C., Starflinger J., Schulenberg T., Laurien E., ...
  • Schulenberg T., Starflinger J., Core Design Concepts for High Performance ...
  • Schulenberg T., Starflinger J., Heinecke J., Three Pass Core Design ...
  • Fischer K., Schulenberg T., Laurien E., Design of a Supercritical ...
  • Herbell H., Himmel S., Schulenberg T., Mechanical Analysis of an ...
  • Bitterman D., Squarer D., Schulenberg T., Oka Y., Dumaz P., ...
  • Brandauer M., Schlagenhaufer M., Schulenberg T., Steam Cycle Optimization for ...
  • Fischer K., Design of a Supercritical Water - Cooled Reactor ...
  • Zhang L., Bao Y., Tang R., Selection and Corrosion Evaluation ...
  • Buongiorno J., Hu L., Two-Phase Heat Transfer in Water-Based Nanofluids ...
  • Salehi D., Jahanfarnia G., Zarifi E., Thermal-Hydraulic Analysis of Al۲O۳ ...
  • Choi S., Eastman J., “Enhancing Thermal Conductivity of Fluids with ...
  • Saidur R., Leongb K., Mohammad H., A Review on Applications ...
  • Zarifi E., Jahanfarnia G., Veysi F., Thermal-Hydraulic Modeling of Nanofluids ...
  • Safarzadeh O., Shirani A., Minuchehr A., Saadatian-derakhshandeh F., Coupled Neutronic/Thermo-Hydraulic ...
  • Nourollahi R., Esteki M. H., Jahanfarnia G., Neutronic Analysis of ...
  • Rahimi M., Jahanfarnia G., Vosoughi N., Thermal–Hydraulic Analysis of Nanofluids ...
  • Waata C. L., Coupled Neutronics, Thermal–Hydraulics Analysis of a High ...
  • Rahimi M., Jahanfarnia G., Thermal-Hydraulic Core Analysis of the Vver-۱۰۰۰ ...
  • Rahimi M., Jahanfarnia G., Thermo-hydraulic Analysis of the Supercritical Water-Cooled ...
  • Hagrman D., Reymann G., “MATPRO-Version ۱۱: A Handbook of Materials ...
  • Luscher W., Geelhood K., Material Property Correlations: Comparisons Between FRAPCON-۳.۴, ...
  • Todreas N.E., Kazimi M.S., Nuclear Systems - Thermal Hydraulic Fundamentals, ...
  • Hosseini S.A., Athari Allaf M., Implementation and Benchmarking of ENDFVII ...
  • Conti A., Impact of Neutron Thermal Scattering Laws on the ...
  • Bahrevar M. H., Jahanfarnia G., pazirandeh A., Shayesteh M., Thermal-Hydraulic ...
  • Barragán-Martínez A.M., Martin-del-Campo C., François J. L., Espinosa-Paredes G., MCNPX ...
  • Atashafrooz, M., Influence of Radiative Heat Transfer on the Thermal ...
  • Zarifi E., Jahanfarnia G., Veysi F., Neutronic Simulation of Water-Based ...
  • Mirghaffari R., Jahanfarnia G., Athariallaf M.,Neutronic Simulation of a Candu-۶ ...
  • MHD Convection of an Al۲O۳–Cu/Water Hybrid Nanofluid in an Inclined Porous Cavity with Internal Heat Generation/Absorption [مقاله ژورنالی]
  • Sajjadi H., Amiri Delouei A., Atashafrooz M., Sheikhol Eslami M., ...
  • نمایش کامل مراجع