Basic design of the TEPLATOR core - construction
Identifikátory výsledku
Kód výsledku v IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F49777513%3A23220%2F20%3A43960520" target="_blank" >RIV/49777513:23220/20:43960520 - isvavai.cz</a>
Výsledek na webu
<a href="https://arhiv.djs.si/proc/nene2020/pdf/NENE2020_0402.pdf" target="_blank" >https://arhiv.djs.si/proc/nene2020/pdf/NENE2020_0402.pdf</a>
DOI - Digital Object Identifier
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Alternativní jazyky
Jazyk výsledku
angličtina
Název v původním jazyce
Basic design of the TEPLATOR core - construction
Popis výsledku v původním jazyce
The study shows the base optimization of the TEPLATOR core. One of the most difficult challenges for this concept is dealing with irradiated fuel assemblies. Because spent nuclear fuel has insufficient reactivity, the main aim of this study is to investigate various effects on TEPLATOR operation from the perspective of the core design. The analysis was executed by Serpent and TRITON code and shows the influence of individual components of the TEPLATOR CORE. The crucial role plays the choice of a suitable moderator; it determines the construction fundamentals of the core. Based on this choice an ideal fuel pitch, a dimension of a reflector, and parameters of cooling were arranged. The construction with or without fuel channels was dealt with. After consideration of all these effects, the first core of this kind was designed. The first DEMO is designed with 50 MW of thermal power and 55 spent fuel assemblies of VVER-440 type in the core, heavy water as both moderator and coolant. More is described in the article.
Název v anglickém jazyce
Basic design of the TEPLATOR core - construction
Popis výsledku anglicky
The study shows the base optimization of the TEPLATOR core. One of the most difficult challenges for this concept is dealing with irradiated fuel assemblies. Because spent nuclear fuel has insufficient reactivity, the main aim of this study is to investigate various effects on TEPLATOR operation from the perspective of the core design. The analysis was executed by Serpent and TRITON code and shows the influence of individual components of the TEPLATOR CORE. The crucial role plays the choice of a suitable moderator; it determines the construction fundamentals of the core. Based on this choice an ideal fuel pitch, a dimension of a reflector, and parameters of cooling were arranged. The construction with or without fuel channels was dealt with. After consideration of all these effects, the first core of this kind was designed. The first DEMO is designed with 50 MW of thermal power and 55 spent fuel assemblies of VVER-440 type in the core, heavy water as both moderator and coolant. More is described in the article.
Klasifikace
Druh
D - Stať ve sborníku
CEP obor
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OECD FORD obor
20305 - Nuclear related engineering; (nuclear physics to be 1.3);
Návaznosti výsledku
Projekt
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Návaznosti
S - Specificky vyzkum na vysokych skolach
Ostatní
Rok uplatnění
2020
Kód důvěrnosti údajů
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Údaje specifické pro druh výsledku
Název statě ve sborníku
Proceedings : 29th International Conference Nuclear Energy for New Europe (NENE 2020)
ISBN
978-961-6207-49-2
ISSN
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e-ISSN
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Počet stran výsledku
7
Strana od-do
"402.1"-"402.7"
Název nakladatele
Nuclear Society of Slovenia
Místo vydání
Ljubljana
Místo konání akce
on-line, Portorož, Slovenia
Datum konání akce
7. 9. 2020
Typ akce podle státní příslušnosti
WRD - Celosvětová akce
Kód UT WoS článku
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