Analysis of possibilities for use of III. and IV. generation of nuclear reactors for the Czech Republic [PDF]
, 2010 Diplomová práce se zabývá analýzou možností užití jaderných reaktorů III. a IV. generace v České republice. Úvodní část se zabývá základními principy jaderné energetiky a palivovým cyklem, který s problematikou úzce souvisí a jeho vývoj a aplikace v ...
Gajdzica, Lukáš
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Overview of Security Plan for Offshore Floating Nuclear Plant [PDF]
, 2018 A new Offshore Floating Nuclear Plant (OFNP) concept with high potential for attractive economics and an unprecedented level of safety is presented, along with an overview of work done in the area of security.
Birch, Arthur +6 more
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Assessment of the size of the Khmelnytskyi NPP observation zone taking into account power units No. 5 and 6 with the AP1000 reactor [PDF]
Ядерна фізика та енергетикаAn assessment of the size of the observation zone (OZ) of the Khmelnytskyi NPP was carried out, taking into account the potential impact of power units No. 3 and 4 with the VVER-1000 reactor and No.
М. М. Тalerko +5 more
doaj +1 more source
Investigation of Ageing Effects Using the Probabilistic Safety Assessments - Proceedings of the European Workshop on Probabilistic Safety Assessment [PDF]
, 2011 JRC – IE Petten organized with the support of the Kernkraftwerk Gösgen-Däniken, Switzerland, an EC Workshop on Investigation of Ageing Effects using the Probabilistic Safety Assessments.
NITOI MIRELA
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Investigation of Microstructure, Mechanical Properties and Irradiation Behaviors of Nuclear Application Steels [PDF]
, 2015 在核能领域应用的关键材料的服役条件非常苛刻，需要在辐照、高温、腐蚀、受应力、热循环等极端条件下长期稳定工作，并按照可预期的方式老化、失效。堆内构件的性能与特性决定了核能可以达到的安全水平。中国从美国西屋公司引进、吸收与消化AP1000核电技术，以形成具有自主知识产权的核电技术，并在此过程中着重对一系列核能关键用材料进行了相关研发。本论文以国产SA-182F304钢、304SS钢、CNST1钢、CNST2钢和CNSS3钢为研究对象，对候选钢的微观结构、微观化学、力学行为和抗辐照性能进行了详细研究 ...
陈芙梁
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Risk-Informed design process of the IRIS reactor [PDF]
, 2005 Westinghouse is currently conducting the pre-application licensing of the International Reactor Innovative and Secure (IRIS). The design philosophy of the IRIS has been based on the concept of Safety-by-DesignTM and within this framework the PSA is ...
A. MAIOLI +5 more
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In-Vessel Melt Retention (IVMR) Analysis of a VVER-1000 NPP [PDF]
, 2016 As part of the outcome of the EU “Stress Tests” in 2012, several areas for further research in the field of Severe Accident Management have been identified for different types of NPPs.
BAJARD Sophie +21 more
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Nuclear Energy in the UK: Safety Culture and Industrial Organisation [PDF]
, 2014 In this paper we seek to explore the relationship between professionalism and nuclear safety in the UK. We consider the history of civil nuclear energy in Britain and the near complete shift in emphasis from state owned enterprises to the private sector.
Earp, John E., Nuttall, William J.
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Nuclear Engineering and TechnologyIn-vessel retention through external reactor vessel cooling (IVR-ERVC) is a severe accident management (SAM) strategy that has been adopted and used in many nuclear reactors such as AP1000, APR1400, and light water reactor etc.
Hyeongi Moon +3 more
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EnergiesThe demand for the power grid system’s capacity to undergo peak-shaving is increasing as the proportion of renewable energy rises. In China, nuclear power units usually only provide a base load operation in the view of safety and economic considerations,
Lingkai Zhu +5 more
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