Simulace havárii bazénu vyhořelého jaderného paliva
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Date
Authors
Strieš, Jakub
ORCID
Advisor
Referee
Mark
A
Journal Title
Journal ISSN
Volume Title
Publisher
Vysoké učení technické v Brně. Fakulta elektrotechniky a komunikačních technologií
Abstract
Cieľom diplomovej práce je poskytnúť teoretický podklad pre simulovanie havárií bazenu s vyhoretým jadrovým palivom a pokúsiť sa zostaviť pracujúci model v prostredí Melcor. Práca je rozdelená do štyroch hlavných častí. V prvej časti sa nachádza popis vyhoretého paliva. Popísané sú deje, ktoré prebiehajú v jadrovom palive a vedú tak k vzniku vyhoretého paliva. Sú tu popísané dôvody nutnosti chladenia jadrového paliva po jeho pôsobení v reaktore. Popísaný je napríklad vznik zbytkového tepla. Nasleduje popis základných časti a účel bazénu s vyhoretým jadrovým palivom. Ukázané sú konštrukčné časti, meracie systémy či požiadavky na samotný bazén. Následne je v tejto kapitole umiestnený aj prehľad nehôd v bazéne s vyhoretým palivom ktoré v minulosti nastali. Sú popísané ich príčiny a dôsledky ale hlavne ich vplyv na ďalší vývoj jadrovej bezpečnosti najmä v oblasti bazénov s vyhoretým palivom. Pre popis aj následnu simuláciu boli vybrané dve najviac skúmané, a to porucha so stratou chladenia a porucha so stratou chladiva. Tretia časť priblížuje program Melcor ktorý, je hlavným nástrojom na vytvorenie simulačného modelu. Kapitola obsahuje základny popis programu ako aj priblíženie modulov ktoré, sú určené špecialne na simulácie bazénov s vyhoretým palivom. Náplňou poslednej časti je popis použitého modelu, jeho tvorba, úprava, problémy pri jeho tvorbe a ich riešenie. V závere sú ukázané a popísané dosiahnuté výsledky spolu s komentárom dopĺňajúcim ich pochopenie.
The aim of the thesis is to provide a theoretical basis for simulating spent fuel pool accidents and to try to build a working model in the Melcor environment. The thesis is divided into four main parts. In the first part a description of the spent fuel pool is given. The processes that take place in nuclear fuel and thus lead to the formation of spent fuel are described. The reasons for the need to cool nuclear fuel after it has been in the reactor are described. For example, the generation of residual heat is described. This is followed by a description of the basic parts and purpose of a spent fuel pool. Structural parts, measuring systems or requirements for the pool itself are shown. Subsequently, an overview of accidents in spent fuel pools that have occurred in the past is also included in this chapter. Their causes and consequences are described, but especially their impact on the further development of nuclear safety, especially in the field of spent fuel pools. For both description and subsequent simulation, the two most studied ones, namely the loss-of-cooling failure and the loss-of-coolant failure, have been selected. The third section introduces the Melcor program which, is the main tool to create the simulation model. The chapter contains a basic description of the program as well as an introduction to the modules that are specifically designed for spent fuel pool simulations. The last part is a description of the model used, its creation, modification, problems in its creation and their solution. Finally, the results obtained are shown and described, together with a commentary to complete their understanding.
The aim of the thesis is to provide a theoretical basis for simulating spent fuel pool accidents and to try to build a working model in the Melcor environment. The thesis is divided into four main parts. In the first part a description of the spent fuel pool is given. The processes that take place in nuclear fuel and thus lead to the formation of spent fuel are described. The reasons for the need to cool nuclear fuel after it has been in the reactor are described. For example, the generation of residual heat is described. This is followed by a description of the basic parts and purpose of a spent fuel pool. Structural parts, measuring systems or requirements for the pool itself are shown. Subsequently, an overview of accidents in spent fuel pools that have occurred in the past is also included in this chapter. Their causes and consequences are described, but especially their impact on the further development of nuclear safety, especially in the field of spent fuel pools. For both description and subsequent simulation, the two most studied ones, namely the loss-of-cooling failure and the loss-of-coolant failure, have been selected. The third section introduces the Melcor program which, is the main tool to create the simulation model. The chapter contains a basic description of the program as well as an introduction to the modules that are specifically designed for spent fuel pool simulations. The last part is a description of the model used, its creation, modification, problems in its creation and their solution. Finally, the results obtained are shown and described, together with a commentary to complete their understanding.
Description
Citation
STRIEŠ, J. Simulace havárii bazénu vyhořelého jaderného paliva [online]. Brno: Vysoké učení technické v Brně. Fakulta elektrotechniky a komunikačních technologií. 2024.
Document type
Document version
Date of access to the full text
Language of document
sk
Study field
bez specializace
Comittee
Ing. Branislav Bátora, Ph.D. (člen)
Ing. Jan Morávek, Ph.D. (člen)
Ing. Tomáš Ondračka, Ph.D. (člen)
doc. Ing. Pavel Zácha, Ph.D. (člen)
doc. Ing. Jaroslava Orságová, Ph.D. (předseda)
doc. Ing. Petr Baxant, Ph.D. (místopředseda)
prof. Ing. Karel Katovský, Ph.D. (člen)
Date of acceptance
2024-06-06
Defence
Student seznámil komisi s výsledky své diplomové práce. S posudky seznámili komisi vedoucí práce Ing. Mičian a oponent Dr. Foral. Vedoucí práce hodnotil stupněm A s 90 b. Oponent hodnotil stupněm A s 91 b. Následnou rozpravu zahájil Dr. Foral položením otázek oponenta. Doplňující dotaz položil doc. Zácha na důvod ventilace budovy nad bazénem. Studen pohotově zodpověděl otázky.
Result of defence
práce byla úspěšně obhájena
Document licence
Standardní licenční smlouva - přístup k plnému textu bez omezení