Vše

Co hledáte?

Vše
Projekty
Výsledky výzkumu
Subjekty

Rychlé hledání

  • Projekty podpořené TA ČR
  • Významné projekty
  • Projekty s nejvyšší státní podporou
  • Aktuálně běžící projekty

Chytré vyhledávání

  • Takto najdu konkrétní +slovo
  • Takto z výsledků -slovo zcela vynechám
  • “Takto můžu najít celou frázi”

Feasibility study of a prestressed-concrete containment vessel for a novel GFR nuclear reactor

Identifikátory výsledku

  • Kód výsledku v IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F46356088%3A_____%2F23%3AN0000010" target="_blank" >RIV/46356088:_____/23:N0000010 - isvavai.cz</a>

  • Nalezeny alternativní kódy

    RIV/68407700:21110/23:00366069

  • Výsledek na webu

    <a href="https://www.sciencedirect.com/science/article/pii/S0141029623005333" target="_blank" >https://www.sciencedirect.com/science/article/pii/S0141029623005333</a>

  • DOI - Digital Object Identifier

    <a href="http://dx.doi.org/10.1016/j.engstruct.2023.116119" target="_blank" >10.1016/j.engstruct.2023.116119</a>

Alternativní jazyky

  • Jazyk výsledku

    angličtina

  • Název v původním jazyce

    Feasibility study of a prestressed-concrete containment vessel for a novel GFR nuclear reactor

  • Popis výsledku v původním jazyce

    The latest modern nuclear energy systems currently researched and developed are the Generation IV (Gen IV) nuclear reactors, and one of the more promising Gen IV designs is the Gas-cooled fast reactor (GFR). Among the number of challenging problems of the design of GFR, the development of passive safety systems ensuring passive decay heat removal (DHR) during loss-of-coolant-accidents (LOCA) is of the highest importance. The currently proposed DHR strategy relies on intentionally increasing pressure inside a gas-tight guard vessel containing the reactor to approximately 4 bar. This, however, presents a significant engineering challenge as the vessel must be capable of withstanding high pressure of up to 10 bar, due to pressure spikes and safety coefficients, while also withstanding increased temperatures during the LOCA. As no GFR guard vessel has ever been designed, this paper presents a feasibility study establishing whether such vessel can be designed. The feasibility study is aimed at the assessment of a preconceptual design of a prestressed concrete vessel previously created by the authors. In the study, stresses in the structure induced by normal-operation loads and LOCA loads are calculated for three types of extreme constraint conditions covering all possible real constraints of the structure. The calculations are based on heat transfer equations, Euler-Bernoulli theory, and Lame equation implemented in a in-house Python code. In the results, stresses in the vessel are presented and compared to design criteria. The main conclusion of the paper is that the vessel can be designed; however, certain adverse phenomena which complicate the design process, such as non-linear creep of concrete and occurrence of tensile stress up to 1 MPa, will have to be addressed and considered during future detailed design. Following on from this affirmative conclusion, the authors will create the detailed design using advanced three-dimensional modelling in their future work.

  • Název v anglickém jazyce

    Feasibility study of a prestressed-concrete containment vessel for a novel GFR nuclear reactor

  • Popis výsledku anglicky

    The latest modern nuclear energy systems currently researched and developed are the Generation IV (Gen IV) nuclear reactors, and one of the more promising Gen IV designs is the Gas-cooled fast reactor (GFR). Among the number of challenging problems of the design of GFR, the development of passive safety systems ensuring passive decay heat removal (DHR) during loss-of-coolant-accidents (LOCA) is of the highest importance. The currently proposed DHR strategy relies on intentionally increasing pressure inside a gas-tight guard vessel containing the reactor to approximately 4 bar. This, however, presents a significant engineering challenge as the vessel must be capable of withstanding high pressure of up to 10 bar, due to pressure spikes and safety coefficients, while also withstanding increased temperatures during the LOCA. As no GFR guard vessel has ever been designed, this paper presents a feasibility study establishing whether such vessel can be designed. The feasibility study is aimed at the assessment of a preconceptual design of a prestressed concrete vessel previously created by the authors. In the study, stresses in the structure induced by normal-operation loads and LOCA loads are calculated for three types of extreme constraint conditions covering all possible real constraints of the structure. The calculations are based on heat transfer equations, Euler-Bernoulli theory, and Lame equation implemented in a in-house Python code. In the results, stresses in the vessel are presented and compared to design criteria. The main conclusion of the paper is that the vessel can be designed; however, certain adverse phenomena which complicate the design process, such as non-linear creep of concrete and occurrence of tensile stress up to 1 MPa, will have to be addressed and considered during future detailed design. Following on from this affirmative conclusion, the authors will create the detailed design using advanced three-dimensional modelling in their future work.

Klasifikace

  • Druh

    J<sub>imp</sub> - Článek v periodiku v databázi Web of Science

  • CEP obor

  • OECD FORD obor

    20501 - Materials engineering

Návaznosti výsledku

  • 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)

Ostatní

  • Rok uplatnění

    2023

  • Kód důvěrnosti údajů

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

Údaje specifické pro druh výsledku

  • Název periodika

    Engineering Structures

  • ISSN

    0141-0296

  • e-ISSN

    1873-7323

  • Svazek periodika

    286

  • Číslo periodika v rámci svazku

    April

  • Stát vydavatele periodika

    GB - Spojené království Velké Británie a Severního Irska

  • Počet stran výsledku

    22

  • Strana od-do

    1-22

  • Kód UT WoS článku

    000981743900001

  • EID výsledku v databázi Scopus

    2-s2.0-85152131899