Neutronic performance of VVER-1200 reactor with advanced fuel and cladding materials
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F23%3A00364156" target="_blank" >RIV/68407700:21340/23:00364156 - isvavai.cz</a>
Result on the web
<a href="https://doi.org/10.1016/j.nucengdes.2023.112216" target="_blank" >https://doi.org/10.1016/j.nucengdes.2023.112216</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1016/j.nucengdes.2023.112216" target="_blank" >10.1016/j.nucengdes.2023.112216</a>
Alternative languages
Result language
angličtina
Original language name
Neutronic performance of VVER-1200 reactor with advanced fuel and cladding materials
Original language description
Nuclear reactor operation and safety are connected with a nuclear fuel design and its material and geometry properties. An increase in nuclear safety is therefore based on a neutronic and thermal analysis of the materials used in a core. This paper analyzes neutronic properties of a VVER-1200 fuel assembly with alternate fuel and cladding materials that consider Accident Tolerant or Advanced Technology Fuels (ATF). The ATF nuclear fuel development started with the post-Fukushima efforts and its main purpose is a reduction of the high-temperature hydrogen production from the zirconium water reaction. Five ATF cladding candidates with reference Zr-based alloy are studied in this paper as well as six ATF fuel candidates together with an additional standard UO2 reference case. The results are analysed based on the multiplication characteristics, reactivity feedbacks, and spent nuclear fuel composition.
Czech name
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Czech description
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Classification
Type
J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database
CEP classification
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OECD FORD branch
20305 - Nuclear related engineering; (nuclear physics to be 1.3);
Result continuities
Project
<a href="/en/project/TK03020034" target="_blank" >TK03020034: Utilization of Advanced Materials for New Types of Nuclear Fuels</a><br>
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Others
Publication year
2023
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Name of the periodical
Nuclear Engineering and Design
ISSN
0029-5493
e-ISSN
1872-759X
Volume of the periodical
405
Issue of the periodical within the volume
04
Country of publishing house
NL - THE KINGDOM OF THE NETHERLANDS
Number of pages
11
Pages from-to
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UT code for WoS article
000942085400001
EID of the result in the Scopus database
2-s2.0-85148003488