XS data preparation for 3D full core calculations
The result's identifiers
Result code in 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>
Result on the web
<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>
Alternative languages
Result language
angličtina
Original language name
XS data preparation for 3D full core calculations
Original language description
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%).
Czech name
—
Czech description
—
Classification
Type
D - Article in proceedings
CEP classification
—
OECD FORD branch
20305 - Nuclear related engineering; (nuclear physics to be 1.3);
Result continuities
Project
<a href="/en/project/EF16_013%2F0001790" target="_blank" >EF16_013/0001790: Strengthening and development of research at Czech Technical University in Prague with the use of research infrastructure VR?1 Training Reactor for research activities</a><br>
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)<br>S - Specificky vyzkum na vysokych skolach
Others
Publication year
2020
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Article name in the collection
2020 21st International Scientific Conference on Electric Power Engineering (EPE)
ISBN
978-1-7281-9479-0
ISSN
—
e-ISSN
2376-5623
Number of pages
5
Pages from-to
383-387
Publisher name
Czechoslovakia Section IEEE
Place of publication
Prague
Event location
Prague
Event date
Oct 19, 2020
Type of event by nationality
WRD - Celosvětová akce
UT code for WoS article
000703899600072