XS data preparation for 3D full core calculations

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F20%3A00345791" target="_blank" >RIV/68407700:21340/20:00345791 - isvavai.cz</a>

Výsledek na webu

<a href="http://dx.doi.org/10.1109/EPE51172.2020.9269255" target="_blank" >http://dx.doi.org/10.1109/EPE51172.2020.9269255</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1109/EPE51172.2020.9269255" target="_blank" >10.1109/EPE51172.2020.9269255</a>

Jazyk výsledku

angličtina

Název v původním jazyce

XS data preparation for 3D full core calculations

Popis výsledku v původním jazyce

Nuclear safety is the essential aspect of the nuclear power plant operation. The safety is based on the well prepared fuel loading pattern that is created with using 3D full core calculations. The calculations are conducted with the simplified geometry and simplified neutron transport solvers (called macrocodes) in industry based process. The simplified calculation approach is efficient with reduced calculation costs, however the specific library of the macroscopic cross-sections have to be prepared. The library is calculated using deterministic or stochastic lattice codes. The macroscopic cross-sections are affected by the calculation approach, moreover they provide connections of the mathematical solution with the physic meaning. The macroscopic cross-sections are compared in the paper. The main problem of the deterministic calculation codes is self-shielding simulation. The presented approach shows relatively good results consistency with the stochastic code. Otherwise, the XS are affected by the self-shielding methodology in higher scale than the multiplication factor. The XS calculated via different code represents reasonably good compliance, however the transport XS is highly affected by the approach (up to 30 %) or code used for data preparation process (up to 50%).

Název v anglickém jazyce

XS data preparation for 3D full core calculations

Popis výsledku anglicky

Nuclear safety is the essential aspect of the nuclear power plant operation. The safety is based on the well prepared fuel loading pattern that is created with using 3D full core calculations. The calculations are conducted with the simplified geometry and simplified neutron transport solvers (called macrocodes) in industry based process. The simplified calculation approach is efficient with reduced calculation costs, however the specific library of the macroscopic cross-sections have to be prepared. The library is calculated using deterministic or stochastic lattice codes. The macroscopic cross-sections are affected by the calculation approach, moreover they provide connections of the mathematical solution with the physic meaning. The macroscopic cross-sections are compared in the paper. The main problem of the deterministic calculation codes is self-shielding simulation. The presented approach shows relatively good results consistency with the stochastic code. Otherwise, the XS are affected by the self-shielding methodology in higher scale than the multiplication factor. The XS calculated via different code represents reasonably good compliance, however the transport XS is highly affected by the approach (up to 30 %) or code used for data preparation process (up to 50%).

Druh

D - Stať ve sborníku

CEP obor

—

OECD FORD obor

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Projekt

<a href="/cs/project/EF16_013%2F0001790" target="_blank" >EF16_013/0001790: Posílení a rozvoj výzkumu na ČVUT v Praze s využitím výzkumné infrastruktury VR-1- Školní reaktor pro výzkumnou činnost</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)<br>S - Specificky vyzkum na vysokych skolach

Rok uplatnění

2020

Kód důvěrnosti údajů

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

Název statě ve sborníku

2020 21st International Scientific Conference on Electric Power Engineering (EPE)

ISBN

978-1-7281-9479-0

ISSN

—

e-ISSN

2376-5623

Počet stran výsledku

5

Strana od-do

383-387

Název nakladatele

Czechoslovakia Section IEEE

Místo vydání

Prague

Místo konání akce

Prague

Datum konání akce

19. 10. 2020

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

000703899600072