Two-dimensional transient thermal analysis of a fuel rod by finite volume method
Brazilian Journal of Radiation Sciences, 2021 One of the greatest concerns when studying a nuclear reactor is the warranty of safe temperature limits all over the system at all times. The preservation of core structure along with the constraint of radioactive material into a controlled system are ...
Rhayanne Yalle Negreiros Costa +2 more
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Construction of staples in lattice gauge theory on a parallel computer
, 1994 We propose a simple method to construct staples in lattice gauge theory with Wilson action on a parallel computer. This method can be applicable to any dimensional system and to any dimensional division without difficulty.
Iwasaki, S. Hioki
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Sensitivity Evaluation of AP1000 Nuclear Power Plant Best Estimation Model
Science and Technology of Nuclear Installations, 2017 The best estimation process of AP1000 Nuclear Power Plant (NPP) requires proper selections of parameters and models so as to obtain the most accurate results compared with the actual design parameters.
Hao Shi, Qi Cai, Yuqing Chen
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Nuclear Engineering and Technology, 2019 It is essential to predict the radioactivity distribution around the reactor cooling system (RCS) during obligatory cyclic operation of AP-1000. A home-developed program CPA-AP1000 is upgraded to predict the response of activated corrosion products (ACPs)
Fiaz Mahmood +4 more
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Analisis Perbandingan Kinerja Perangkat Bahan Bakar Pltn Tipe Pwr Ap 1000 Dan Pwr 1000 Mwe Tipikal Dengan Menggunakan Program Komputer [PDF]
, 2014 Investigation of fuel element thermal-hydraulic characteristic is important step related to aspect of fuel bundle reactor design. This paper analyzes of the PWR AP1000 and PWR 1000 MWe Typical of fuel bundle thermal-hydraulic using RELAP5 code.
Nurmawan, A. (Arif) +2 more
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Nuclear Engineering and Technology, 2013 The Critical Heat Flux (CHF) of water with dispersed alumina nanoparticles was measured for the geometry and flow conditions relevant to the In-Vessel Retention (IVR) situation which can occur during core melting sequences in certain advanced Light Water
G. DEWITT +4 more
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Estudio de la termo-hidráulica del tanque de agua de recarga (IRWST) en el reactor AP1000® durante un accidente tipo SBLOCA con el código GOTHIC 8.1. [PDF]
, 2016 El reactor AP1000 se caracteriza por el uso de sistemas pasivos para refrigerar el reactor en caso de accidente. Uno de los sistemas más importantes, es el sistema pasivo de refrigeración del núcleo en emergencia (PXS), el cual, incluye uno de los ...
Estévez Albuja, Samanta Estefanía +3 more
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Research on the Preparation and Properties of Iron-based Composites Used as Neutron Absorbing in Gray Control Rod [PDF]
, 2016 中国已从美国西屋公司引进、吸收和消化AP1000核电技术。为了形成自主知识产权的关键核电技术，本文对堆芯关键部件灰控制棒用中子吸收体材料进行了相关研究。基于前期对多种元素的核特性及燃耗分析获得了几种符合灰控制棒性能要求的候选元素，如Tm、Tb和Dy。本文采用粉末冶金方法(高能球磨、冷等静压与烧结)制备出了两种堆芯灰控制棒用中子吸收材料Fe-Tm2O3和Fe-TbFeO3-DyFeO3芯块。采用材料分析方法对球磨粉末、烧结块体进行了微观组织与微观化学分析与表征 ...
刘腾蛟
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Primääripiirin jäähdytysjärjestelmän kuvaus osana Loviisan lopullista turvallisuusselostetta [PDF]
, 2015 Insinöörityön tarkoituksena oli tarkastella Loviisan ydinvoimalan turvallisuusselosteen lukua 5 Reaktorin jäähdytysjärjestelmä. Luvun rakenteeseen oli tarkoitus antaa kehitysehdotuksia ja alalukuun 5.1.
Hannola, Paula
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Numerical investigation of the thermal-hydraulic characteristics of AP1000 steam generator U-tubes
International Journal of Advanced Nuclear Reactor Design and Technology, 2020 Steam generators (SGs) are vital heat exchangers that connect the primary and secondary sides in power plant systems. Based on the AP1000 SG, a numerical model of SG U-tubes is developed.
Zeng-Guang Sui +3 more
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