Analysis of a prestressed-concrete containment vessel exposed to high pressure and temperature

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21110%2F24%3A00360684" target="_blank" >RIV/68407700:21110/24:00360684 - isvavai.cz</a>

Výsledek na webu

<a href="https://dspace.cvut.cz/handle/10467/118501" target="_blank" >https://dspace.cvut.cz/handle/10467/118501</a>

DOI - Digital Object Identifier

—

Jazyk výsledku

angličtina

Název v původním jazyce

Analysis of a prestressed-concrete containment vessel exposed to high pressure and temperature

Popis výsledku v původním jazyce

During the design of any nuclear reactor, a containment structure capable of reliably guarding against fission product release in case of an accident must be designed. In this thesis, the topic of structural feasibility analyses of prestressed-concrete cylindrical containment structures subjected to high pressure and temperature is investigated. The motivation for investigating this specific topic is to solve a practical problem discovered during research and development of a novel type of reactor, which is currently being conducted. The problem is that the novel reactor induces uncommonly high internal pressure during LOCA, and thus, it needs to be established whether a containment structure capable of withstanding the high pressure can be designed. In the thesis, three main problems are investigated and resolved. These three main problems correspond with three main goals of the thesis. The first main goal of this thesis is to conduct a structural feasibility analysis of a prestressed-concrete containment structure for the novel reactor, and thus, establish whether it is even possible to design a containment structure capable of withstanding the temperatures and high internal pressure induced by the reactor. In order to fulfil the first goal, an associated problem must be resolved. The problem is identifying suitable methods for structural feasibility analyses of prestressed-concrete cylindrical containment walls subjected to high pressure and temperature. Thus, the second main goal of this thesis is to propose a consolidated framework containing all methods, equations, and values needed for the whole process of the feasibility analysis. In order to fulfil this goal, various relevant methods, equations, and design values for the calculation of stresses induced by temperature, pressure, and concrete prestressing are investigated and compared. As the framework contains complex methods which cannot be carried out using manual calculations by hand, a third problem arises. The third problem is implementing the proposed framework in such a way that would enable its expeditious and intuitive use for the feasibility analyses. Thus, the third main goal of this thesis is to create a standalone software application which would implement the proposed framework and allow expeditious and intuitive feasibility analyses of prestressed-concrete cylindrical containment walls. This application may also be highly beneficial for conducting parametric studies, design optimisations, and verifications of results obtained using more complex software.

Název v anglickém jazyce

Analysis of a prestressed-concrete containment vessel exposed to high pressure and temperature

Popis výsledku anglicky

During the design of any nuclear reactor, a containment structure capable of reliably guarding against fission product release in case of an accident must be designed. In this thesis, the topic of structural feasibility analyses of prestressed-concrete cylindrical containment structures subjected to high pressure and temperature is investigated. The motivation for investigating this specific topic is to solve a practical problem discovered during research and development of a novel type of reactor, which is currently being conducted. The problem is that the novel reactor induces uncommonly high internal pressure during LOCA, and thus, it needs to be established whether a containment structure capable of withstanding the high pressure can be designed. In the thesis, three main problems are investigated and resolved. These three main problems correspond with three main goals of the thesis. The first main goal of this thesis is to conduct a structural feasibility analysis of a prestressed-concrete containment structure for the novel reactor, and thus, establish whether it is even possible to design a containment structure capable of withstanding the temperatures and high internal pressure induced by the reactor. In order to fulfil the first goal, an associated problem must be resolved. The problem is identifying suitable methods for structural feasibility analyses of prestressed-concrete cylindrical containment walls subjected to high pressure and temperature. Thus, the second main goal of this thesis is to propose a consolidated framework containing all methods, equations, and values needed for the whole process of the feasibility analysis. In order to fulfil this goal, various relevant methods, equations, and design values for the calculation of stresses induced by temperature, pressure, and concrete prestressing are investigated and compared. As the framework contains complex methods which cannot be carried out using manual calculations by hand, a third problem arises. The third problem is implementing the proposed framework in such a way that would enable its expeditious and intuitive use for the feasibility analyses. Thus, the third main goal of this thesis is to create a standalone software application which would implement the proposed framework and allow expeditious and intuitive feasibility analyses of prestressed-concrete cylindrical containment walls. This application may also be highly beneficial for conducting parametric studies, design optimisations, and verifications of results obtained using more complex software.

Druh

O - Ostatní výsledky

CEP obor

—

OECD FORD obor

20101 - Civil engineering

Projekt

<a href="/cs/project/TK01030116" target="_blank" >TK01030116: Návrh konceptu bezpečnostně důležitých prvků rychlého heliem chlazeného demonstračního reaktoru ALLEGRO</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2024

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů