Results 51 to 60 of about 3,636 (213)
Multicriterion Synthesis of Intelligent Control Systems of Generating Unit of Nuclear Power Station [PDF]
, 2014 The paper is devoted to solution of some problems in nuclear power station generating unit intellectual control systems using genetic algorithms on the basis of control system model development, optimizations methods of their direct quality indices and ...
Jafari Henjani, Seyed Mojtaba +1 more
core +1 more source
, 2015 Tato bakalářská práce se zabývá popisem jednotlivých konstrukčních řešení parogenerátorů. V první části bakalářské práce je popsán počátek jaderného průmyslu v Rusku. Samostatná práce se věnuje jednotlivým konstrukčním řešením. Poslední kapitola detailně
Michalica, Martin
core
Development and Verification of a Spatial Dynamics Code RESTA‐3D for Light Water Reactors
International Journal of Energy Research, Volume 2025, Issue 1, 2025.A neutronics/thermal‐hydraulics (TH) coupled spatial dynamics code, reactor system transient analysis‐three dimensional (RESTA‐3D), has been developed for both static and transient analysis of large advanced light water reactors (LWRs), with a focus on control rod (CR) ejection accidents.
Yong Cui +4 more
wiley +1 more source
Nuclear Engineering and Technology, 2015 The most important advantage of nanoparticles is the increased thermal conductivity coefficient and convection heat transfer coefficient so that, as a result of using a 1.5% volume concentration of nanoparticles, the thermal conductivity coefficient ...
Seyed Mohammad Mousavizadeh +2 more
doaj +1 more source
Возможность использования альтернативных выгорающих поглотителей в реакторе ВВЭР-1000 [PDF]
, 2016 Объектом исследования является водо-водяной реактор ВВЭР-1000 с топливом в виде диоксида урана. Цель работы ― исследование возможности повышения глубины выгорания ядерного топлива в реакторе ВВЭР-1000.
Сливин, Алексей Асхарович
core
International Journal of Energy Research, Volume 2025, Issue 1, 2025.Reactivity‐initiated accidents (RIAs), such as the control rod drop accident (CRDA), are classified as design‐basis accidents (DBAs) in the final safety analysis report (FSAR) of a nuclear power plant (NPP), and investigating these events is crucial.
Seyed Mohammad Hossein Mousakazemi +1 more
wiley +1 more source
Science and Technology of Nuclear Installations, Volume 2019, Issue 1, 2019., 2019 Reactor pressure vessel (RPV) support is a key safety facility which is categorized as Class 1 in the ASME nuclear safety design. The temperature distribution of RPV support is one of the key considerations for the concrete safety contacting with the bottom of the support.
Longkun He +3 more
wiley +1 more source
A method for VVER fuel element cladding reliability prediction [PDF]
Ядерна фізика та енергетика, 2014 Considering a VVER-1000 fuel assembly averaged fuel element (FE), based on the accepted FE cladding damage limit value, the FE cladding failure probability was determined, thus the possibility of this reliability pre-diction by means of controlling the ...
S. M. Pelykh +2 more
doaj
The choice of the fuel assembly for VVER-1000 in a closed fuel cycle based on REMIX-technology
EPJ Nuclear Sciences & Technologies, 2016 This paper shows basic features of different fuel assembly (FA) application for VVER-1000 in a closed fuel cycle based on REMIX-technology. This investigation shows how the change in the water–fuel ratio in the VVER FA affects on the fuel characteristics
Bobrov Evgenii +4 more
doaj +1 more source
Science and Technology of Nuclear Installations, Volume 2025, Issue 1, 2025.Nuclear reactors are subject to strict safety standards due to the critical nature of operational safety. Detecting transients as fast and accurately as possible is essential to reactor safety especially to reduce the human error of operators. In order to enhance this process, artificial intelligence (AI) offers strong opportunities.
Ceyhun Yavuz +2 more
wiley +1 more source