Results 11 to 20 of about 2,771 (221)

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

open access: yesAtom Indonesia, 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.
D.T. Sony Tjahyani
doaj   +4 more sources

Sorting Integers on the AP1000

open access: yes, 2000
Sorting is one of the classic problems of computer science. Whilst well understood on sequential machines, the diversity of architectures amongst parallel systems means that algorithms do not perform uniformly on all platforms.
Lynes, Andrew, Weaver, Lex
core   +2 more sources

Dynamic Analysis of AP1000 Shield Building Considering Fluid and Structure Interaction Effects

open access: yesNuclear Engineering and Technology, 2016
The shield building of AP1000 was designed to protect the steel containment vessel of the nuclear reactor. Therefore, the safety and integrity must be ensured during the plant life in any conditions such as an earthquake.
Jing Li, Jianyun Chen
exaly   +3 more sources

A Fuzzy Probability Algorithm for Evaluating the AP1000 Long Term Cooling System to Mitigate Large Break LOCA [PDF]

open access: yesAtom Indonesia, 2015
Components of nuclear power plants do not always have historical failure data to probabilistically evaluate their reliability characteristics. To overcome this drawback, an alternative approach has been proposed by involving experts to qualitatively ...
J.H. Purba
doaj   +5 more sources

Experimental and Numerical Studies of AP1000 Shield Building considering Fluid-Structure Interaction

open access: yesScience and Technology of Nuclear Installations, 2022
The gravity cooling water tank is a remarkable structural feature of third-generation pressurized water reactor nuclear power plant. To investigate the influence of fluid-structure interaction (FSI) on the seismic response of the structure, this study ...
Zhi Zhang   +3 more
doaj   +2 more sources

Quantitative Assessment of Gaseous Effluents during Routine Operation: A Comparative Study of Planned Nuclear Power Plants at Lubiatowo-Kopalino and Pątnów Sites in Poland

open access: yesScience and Technology of Nuclear Installations
On September 2021, Polish government declared that six pressurized water reactors with combined capacity of 6–9 GWe will be built by 2040 to reduce Poland’s reliance on coal. Due to the adopted schedule, construction of the first nuclear power plant will
Edyta Agata Macieja, Juyoul Kim
doaj   +2 more sources

Model prediction of radioactivity levels in the environment and food around the world’s first AP 1000 nuclear power unit [PDF]

open access: yesFrontiers in Public Health
ObjectivesModel prediction of radioactivity levels around nuclear facilities is a useful tool for assessing human health risks and environmental impacts.
Peng Wang   +11 more
doaj   +2 more sources

Estimation of tritium generation and discharge of the AP1000 reactor based on historical discharge data from the U.S. Pressurized water reactors [PDF]

open access: yesNuclear Technology and Radiation Protection, 2023
During the normal operation of pressurized water reactors, tritium has contributed more than 95 % of the total radioactivity of all the radionuclides discharged into the environment and has been recognized as the key radionuclide in the design ...
Wang Qi
doaj   +1 more source

RESULTS OF VERA APPLICATION TO THE AP1000® PWR STARTUP [PDF]

open access: yesEPJ Web of Conferences, 2021
This paper describes the application of the Virtual Environment for Reactor Applications, VERA, under development by the Consortium for Advanced Simulation of LWRs (CASL) to the core physics analysis of the AP1000 PWR. The AP1000 PWR features an advanced
Franceschini F., Salazar D., Godfrey A.
doaj   +1 more source

A HYBRID MONTE-CARLO-DETERMINISTIC METHOD FOR AP1000 EX-CORE DETECTOR RESPONSE SIMULATION [PDF]

open access: yesEPJ Web of Conferences, 2021
The ex-core detector-response calculation is a typical deep-penetration problem, which is challenging for the Monte Carlo method. The response of the ex-core detector is an important parameter for the safe operation of the nuclear power plants. Meanwhile,
Zheng Qi   +6 more
doaj   +1 more source

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