Rapid preliminary modeling of transport reactor cores

نویسندگان

چکیده

At the present time, JSC Baltiskiy zavod has built and transported to deployment site at Pevek Akademik Lomonosov , a floating nuclear power unit (FNPU), project 20870. There are also three multi-purpose icebreakers of 22220 ( Arktika Sibir Ural ) under construction being different readiness stages. A decision been made build icebreaker, Lider even higher power. Integral reactors developed by OKBM Afrikantov installed in using new assembly-type cores which have not used earlier facilities. great deal preliminary calculation is required give these as advantageous characteristics possible. The paper proposes procedure for rapid modeling with varied operating design characteristics. This can be part modeling. based on combined dimensionless parameter proposed author (Korolev 2009). chart presented model key performance objects reactor NPPs. Eight core options, transport modular or integral design, analyzed.

برای دانلود رایگان متن کامل این مقاله و بیش از 32 میلیون مقاله دیگر ابتدا ثبت نام کنید

اگر عضو سایت هستید لطفا وارد حساب کاربری خود شوید

منابع مشابه

Mathematical modeling of normal pharyngeal bolus transport: a preliminary study.

Dysphagia (difficulty in swallowing) is a common clinical symptom associated with many diseases, such as stroke, multiple sclerosis, neuromuscular diseases, and cancer. Its complications include choking, aspiration, malnutrition, cachexia, and dehydration. The goal in dysphagia management is to provide adequate nutrition and hydration while minimizing the risk of choking and aspiration. It is i...

متن کامل

A simple model of reactor cores for reactor neutrino flux calculations for the KamLAND experiment

KamLAND is a reactor neutrino oscillation experiment with a very long baseline. This experiment successfully measured oscillation phenomena of reactor antineutrinos coming mainly from 53 reactors in Japan. In order to extract the results, it is necessary to accurately calculate time-dependent antineutrino spectra from all the reactors. A simple model of reactor cores and code implementing it we...

متن کامل

ذخیره در منابع من


  با ذخیره ی این منبع در منابع من، دسترسی به آن را برای استفاده های بعدی آسان تر کنید

ژورنال

عنوان ژورنال: Nuclear Energy and Technology

سال: 2021

ISSN: ['2452-3038']

DOI: https://doi.org/10.3897/nucet.7.65310