Results 51 to 60 of about 1,699,034 (145)
Enhancing Resilience through Nuclear Emergency Preparedness at El Dabaa Site
The research utilized advanced PCTRAN and RASCAL software to evaluate the potential radiological impacts of hypothetical accidents, specifically loss‐of‐coolant accident (LOCA) and long‐term station blackout (LTSBO), at the El Dabaa Nuclear Power Plant. Over a span of ten years, comprehensive meteorological data were meticulously analyzed to assess the
Waad Saleh, Juyoul Kim, Doddy Kastanya
wiley +1 more source
Final report. U.S. Department of Energy University Reactor Sharing Program [PDF]
Activities supported at the MIT Nuclear Reactor Laboratory under the U.S. DOE University Reactor Sharing Program are reported for Grant DE FG02-95NE38121 (September 16, 1995 through May 31, 2002).
Bernard, John A.
core +1 more source
Research Status and Development Suggestion of Numerical Reactor
With the rapid development of computer science and technology, numerical simulation has become one of scientific research methods after theory research and experiment research, and it is now playing a very important role in the R&D of nuclear reactors ...
WU Hongchun;LIU Zhouyu;ZHOU Xinyu;CAO Liangzhi
doaj
Investigation of Burst Pressures in PWR Primary Pressure Boundary Components
In a reactor coolant system of a nuclear power plant (NPP), an overpressure protection system keeps pressure in the loop within 110% of design pressure.
Ihn Namgung, Nguyen Hoang Giang
doaj +1 more source
Many reactor safety simulation codes for nuclear power plants (NPPs) have been developed. However, it is very important to evaluate these codes by testing different accident scenarios in actual plant conditions.
Eltayeb Yousif +3 more
doaj +1 more source
Waste and decommissioning [PDF]
This paper is the fifth in a series of 8 that make up the evidence base for SDC report 'The role of nuclear power in a low carbon economy'.This document is an extensive review of the nuclear waste issue, covering radioactive waste management in both ...
AMEC NNC Limited +2 more
core +2 more sources
Assessment of cost and schedule performance in construction of key nuclear reactors
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 +2 more
doaj +1 more source
The Passive Heat Removal system (PHRS) is designed to remove the residual heat from the core in case of a station blackout, failure of emergency core cooling system, or failure of feedwater supply through the Passive Residual Heat Removal Heat Exchanger (PRHR HX).
Mantasha Ponkty +2 more
openaire +1 more source
Westinghouse AP1000 Plant, a Generation III+ Reactor
In a first part, this paper describes the AP1000® pressurized water reactor (PWR) design and how the AP1000 plant fundamental objectives of safety, simplification and standardization were applied throughout the design of the AP1000 plant.
Julie Gorgemans +2 more
core +1 more source
Technical and Economic Comparative Analysis of Nuclear Power Plants: AP1000 and SMR
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 +4 more
doaj +1 more source

