Results 51 to 60 of about 130 (115)

Assessment of cost and schedule performance in construction of key nuclear reactors

Будівельні конструкції. Теорія і практика
The nuclear industry is a unique sector that is especially vulnerable to delays. A multitude of impactful factors such as the complexity of design, tight on-site schedules, and a logistically sophisticated end-to-end supply chain, to name just a few ...
Кароль Скіба, Міхал Рогуз, Роман Кінаш   +2 more
doaj   +1 more source

Technical and Economic Comparative Analysis of Nuclear Power Plants: AP1000 and SMR

Energies
Due to the necessity of decarbonising and transforming the Polish energy mix, topic of using nuclear power plants as one of the key low-carbon generation sources is returning to the public debate.
Natalia Kasińska, Agata Mielcarek, Jakub Sierchuła, Radosław Szczerbowski, Bartosz Ceran   +4 more
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Development and Application of Deterministic Numerical Reactor Code NECP-X

Yuanzineng kexue jishu, 2022
Based on the large-scale parallel computing platform, the numerical reactor uses advanced physical models, numerical simulation algorithms and fined modeling, so as to accurately simulate various physical phenomena of the reactor under normal operation ...
LIU Zhouyu;XU Xiaobei;WEN Xingjian;WANG Bo;CAO Lu;ZHOU Xinyu;ZHANG Minwan;CHEN Junji;WANG Xining;LI Fan;LI Shuaizheng;MA Shengze;SHAO Shihao;CAO Liangzhi;WU Hongchun
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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 енергетика
An 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, Т. D. Lev, А. V. Nosovskyi, V. М. Rudko, А. М. Novikov, O. V. Blokhina   +5 more
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In-depth investigation of natural convection thermal characteristics of BALI experiment through Eulerian computational fluid dynamics code and comparison with Lagrangian code

Nuclear Engineering and Technology
In-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, Sohyun Park, Eungsoo Kim, Jae-Ho Jeong   +3 more
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Study of Load Adjustment Strategy for Nuclear Power Units Focusing on Rankine Cycle: Flexibility–Environment–Economy

Energies
The 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, Wei Zheng, Wenxing Wang, Ziwei Zhong, Junshan Guo, Jiwei Song   +5 more
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Analysis for the Effect of Spatial Discretization Method on AP1000 Reactor Pressure Vessel Fluence Calculation

Science and Technology of Nuclear Installations, 2016
Maintaining the structural integrity of the reactor pressure vessel (RPV) is a critical concern related to the safe operation of nuclear power plants. To estimate the structural integrity over the designed lifetime and to support analyses for a potential
Junxiao Zheng, Bin Zhang, Shengchun Shi, Yixue Chen   +3 more
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Assessment of radiation exposure and public health before and after the operation of Sanmen nuclear power plant. [PDF]

Front Public Health, 2023
Ren H, Yu S, Wang Z, Zheng T, Zou H, Lou X, Wang P, Zhou L, Zhang D, Zhang M, Guo J, Lai Z, Zhao Y, Xuan Z, Cao Y.   +14 more
europepmc   +1 more source

Analysis of the SWOT matrix as a strategy for implementing the Ap-Th1000 Reactor in Brazil

Brazilian Journal of Radiation Sciences
This article analyzes the SWOT Matrix for the implementation of the AP-Th1000 reactor with thorium fuel, aiming at a future replacement of the current nuclear reactors that use uranium as fuel by thorium.
Francky Roger Araujo da Silva, Giovanni Laranjo de Stefani, Marcelo Vilela da Silva   +2 more
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Analysis on Phenomena of HPR1000 Large Break Loss of Coolant Accident Based on TRACE Code

Yuanzineng kexue jishu, 2022
HPR1000 is the Generation Ⅲ pressurized water reactor (PWR)technology independently developed by China. In order to deal with the steam generator tube rupture (SGTR) accident and prevent pressurizer overflow, HPR1000 adopts some new features such as the
SUN Wei;XU Chao;FU Hao;LIU Yusheng
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