Results 31 to 40 of about 1,504 (160)

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, Mário Augusto Bezerra da Silva, Carlos Alberto Brayner de Oliveira Lira   +2 more
doaj   +1 more source

Nuclear Power Sustainability Path for China from the Perspective of Operations

Science and Technology of Nuclear Installations, Volume 2022, Issue 1, 2022., 2022
Nuclear power, as a low‐carbon, stable, and efficient energy, plays an important role in replacing fossil fuels in the development of a globally sustainable energy system. However, nuclear power has deviated from the path to achieve the Sustainable Development Goals of the United Nations.
Tao Zhang, Shengzhi Liu, Weiwei Pan, Tian Wan, Chenhui Dong, Han Zhang   +5 more
wiley   +1 more source

The Implementation of Diverse Actuation System in ACPR1000 Nuclear Power Plants

Science and Technology of Nuclear Installations, Volume 2021, Issue 1, 2021., 2021
In order to improve the capability of dealing with software common cause failure (CCF) of digital reactor protection and monitoring system (RPMS), the diverse actuation system (DAS) is introduced for ACPR1000 nuclear power plants. From economic and feasibility point of view, the solution of DAS sharing with RPMS sensors and actuators is suggested ...
Zhen-Ying Wang, Zhi-Yun Liu, Ting-Wei Ma, Chen Sun, Liu Liu, Yu Huang, Gang-Miao Guo, Massimo Zucchetti   +7 more
wiley   +1 more source

Design, Experiment, and Commissioning of the Passive Residual Heat Removal System of China’s Generation III Nuclear Power HPR1000

Science and Technology of Nuclear Installations, Volume 2021, Issue 1, 2021., 2021
In response to a station blackout accident similar to the Fukushima nuclear accident, China’s Generation III nuclear power HPR1000 designed and developed a passive residual heat removal system connected to the secondary side of the steam generator. Based on the two‐phase natural circulation principle, the system is designed to bring out long‐term core ...
Feng Li, Yazhe Lu, Xiao Chu, Qiang Zheng, Guanghao Wu, Iztok Tiselj   +5 more
wiley   +1 more source

Calculation and Analysis of the Source Term of the Reactor Core Based on Multivariate Analysis of Variance

Science and Technology of Nuclear Installations, Volume 2021, Issue 1, 2021., 2021
The calculation of the core source term is affected by various factors, such as fuel consumption, enrichment, specific power, and operation mode. The activity of lanthanides, fission products, and the photon source strength were calculated using the ORIGEN program. The weights of each factor were calculated by multivariate analysis of variance.
Tao Zhou, Peng Xu, Tian Qi, Xuemeng Qin, Juan Chen, Zhongguang Fu, Arkady Serikov   +6 more
wiley   +1 more source

Neutronic Performance of the VVER‐1000 Reactor Using Thorium Fuel with ENDF Library

Science and Technology of Nuclear Installations, Volume 2021, Issue 1, 2021., 2021
In this paper, neutronic calculations and the core analysis of the VVER‐1000 reactor were performed using MCNP6 code together with both ENDF/B‐VII.1 and ENDF/B‐VIII libraries. The effect of thorium introduction on the neutronic parameters of the VVER‐1000 reactor was discussed.
Sonia M. Reda, Ibrahim M. Gomaa, Ibrahim I. Bashter, Esmat A. Amin, Arkady Serikov   +4 more
wiley   +1 more source

An Advanced TRACE Modeling Approach: Automatic Connection of 3D Cartesian and Cylindrical VESSEL Components in Integral Plant Models

Energies, 2022
Best estimate system thermal-hydraulic codes in the nuclear engineering community, e.g., TRACE, RELAP3D, CATHARE-3, etc., were extended with 3D coarse-mesh components to better describe the 3D Thermal-Hydraulic (TH) phenomena taking place within the ...
Kanglong Zhang, Victor Hugo Sanchez-Espinoza   +1 more
doaj   +1 more source

Reliability Study of the AP1000 Passive Safety System by Fuzzy Approach [PDF]

, 2014
The Westinghouse AP1000 is a new design nuclear power plant which has implemented the concept of passive system. Even though a passive system may be more reliable than an active one, the possibility of the passive system to fail still exists.
Purba, J. H. (J), Sony Tjahyani, D.T
core   +2 more sources

The development of high fidelity Steam Generator three dimensional thermal hydraulic coupling code: STAF-CT

Nuclear Engineering and Technology, 2021
The thermal hydraulic performances of Steam Generator (SG) under both steady and transient operation conditions are of great importance for the safety and economy in nuclear power plants.
Xiaohan Zhao, Mingjun Wang, Ge Wu, Jing Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su   +6 more
doaj   +1 more source

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
doaj   +1 more source