scholarly journals Gamma-ray Analysis of the Pressurized-Water-Reactor and Boiling-Water-Reactor Assemblies

2019 ◽  
Author(s):  
Duc Ta Vo
Keyword(s):  
Gamma Ray ◽  
Boiling Water ◽  
Boiling Water Reactor ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor

Radionuclide Composition of Airborne Discharges of European NPPS With WWER, Pressurized Water Reactor, and Boiling Water Reactor Facilities

2020 ◽  
Vol 7 (1) ◽  
Author(s):  
Angelina-Nataliya V. Vukolova ◽  
Andrei A. Rusinkevich
Keyword(s):  
Power Plants ◽  
Boiling Water ◽  
Normal Operation ◽  
Boiling Water Reactor ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor ◽  
Operation Conditions ◽  
Discharge Activity ◽  
Radionuclide Composition

Abstract The article presents the analysis of the data on radionuclide composition of airborne discharges of 52 European nuclear power plants (NPPs) with water–water energetic reactor facilities (WWER), pressurized water reactor facilities (PWR), and boiling water reactor facilities (BWR) under normal operation conditions. It contains lists of radionuclides, registered in discharges of researched NPPs, and gives estimation of contributions of radionuclides, forming the discharge, into total activity of discharge and into total effective dose, created by the discharge activity. It was determined that the maximal contribution into discharge activity of all researched NPPs make noble gases, tritium, and carbon-14, while the latter is the main dose-making radionuclide.

The Analysis of Pressurized Water Reactor and Boiling Water Reactor Reactivity Transients with CORETRAN and RETRAN-3D

2003 ◽  
Vol 142 (1) ◽  
pp. 19-34 ◽  
Author(s):  
Hakim Ferroukhi ◽  
Paul Coddington
Keyword(s):  
Boiling Water ◽  
Boiling Water Reactor ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor

Irradiation Capabilities at the Halden Reactor and Testing Possibilities Under Supercritical Water Conditions

2016 ◽  
Vol 2 (2) ◽  
Author(s):  
Rudi Van Nieuwenhove
Keyword(s):  
Feasibility Study ◽  
Supercritical Water ◽  
External Pressure ◽  
Boiling Water ◽  
Boiling Water Reactor ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor ◽  
Water Conditions ◽  
Different Types

Different types of instruments have been developed both for in-pile fuel and materials studies at the Halden Reactor Project. In recent years, several of the standard instruments have been upgraded to be able to tolerate much higher temperatures. In particular, several instruments are now able to operate up to 650°C and 25 MPa, thus in the range suitable for supercritical water (SCW) studies. In addition, a feasibility study for an in-pile SCW loop has been carried out that shows that such a loop can be realized in the Halden reactor, allowing for all the instrumentation possibilities that are presently carried out in pressurized water reactor (PWR) and boiling water reactor (BWR) conditions. Another, and cheaper, alternative is to perform corrosion experiments inside a small capsule in which SCW is maintained by means of gamma heating and external pressure lines. The conceptual designs of the SCW loop and SCW capsule will be highlighted.

Análise energética de uma usina nuclear com reator BWR e estudo comparativo com a usina nuclear Angra 2 do modelo PWR

2020 ◽  
Vol 25 (1) ◽  
Author(s):  
Filipe de Almeida da Silva Soares ◽  
Jonni Guiller Ferreira Madeira ◽  
Manuel Luis Pires Clara
Keyword(s):  
Boiling Water ◽  
Boiling Water Reactor ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor

Uma usina nuclear gera energia elétrica através de reações nucleares que ocorrem controladamente em um reator. Este tipo de termoelétrica vem se destacando como uma importante fonte de energia elétrica, principalmente, a elevados fatores de capacidade, domínio da tecnologia e emissão de pequenas quantidades de gases que influenciam no efeito estufa. Os reatores de água fervente (Boiling Water Reactor - BWR) representam 18% do total de reatores nucleares existentes do mundo ficando apenas atrás dos reatores de água pressurizada (Pressurized Water Reactor - PWR). Neste trabalho é apresentado um estudo investigativo onde foi realizada uma análise energética sobre a central nuclear de LaSalle e seus equipamentos. Foi feita, também, uma comparação com os dados encontrados por SIQUEIRA (2016) que realizou um estudo da usina nuclear de Angra 2 do tipo PWR. A usina nuclear analisada é do tipo BWR, com uma capacidade de geração de 1144 MW. A eficiência encontrada do ciclo da planta foi de 34,6%, valor ligeiramente superior ao resultado encontrado num PWR. No entanto, esta diferença se torna significativa quando tem-se que essas centrais funcionam com capacidade superior à 1000MW.

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