Study on Neutronics of VVER-1200 with Accident Tolerant Fuel Cladding
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F19%3A00324364" target="_blank" >RIV/68407700:21340/19:00324364 - isvavai.cz</a>
Result on the web
<a href="https://doi.org/10.1016/j.anucene.2018.10.040" target="_blank" >https://doi.org/10.1016/j.anucene.2018.10.040</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1016/j.anucene.2018.10.040" target="_blank" >10.1016/j.anucene.2018.10.040</a>
Alternative languages
Result language
angličtina
Original language name
Study on Neutronics of VVER-1200 with Accident Tolerant Fuel Cladding
Original language description
Protective coatings deposited on traditional Zr-based fuel cladding materials potentially enhance accidental tolerance of Light Water Reactors due to reduced interaction between water and Zr alloys during accidental conditions. Enhancement of cladding performance and reduction of negative effects, such as heat generation, hydrogen production, oxidation, and embrittlement can be achieved by deposition of various coatings that are widely studied around the world. Even though thermal, mechanical, and chemical responses during accidental conditions are the main concern for these materials, the actual application of coated materials will be linked to standard operating conditions including economic consequences and transient response. Reference VVER-1200 fuel system with five coatings (Cr, CrN, ZrSi2, Cr2AlC, Fe(Cr)(Al)) is investigated from the neutron-physical point of view using the calculation package SCALE 6.2.2. In addition to the multiplication factor, specific fuel safety criteria are also examined for both the fresh fuel assemblies and fuel assemblies with burn-up up-to 70~MWd/tHM. All studied coatings entail certain negative effects in comparison with the reference case. The closest behavior to the reference VVER-1200 fuel assembly is found for ZrSi2 coating followed by Cr2AlC and Fe(Cr)(Al) coatings. Both Cr and CrN materials exhibit significant differences compared to the reference case.
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
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Continuities
S - Specificky vyzkum na vysokych skolach
Others
Publication year
2019
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Name of the periodical
Annals of Nuclear Energy
ISSN
0306-4549
e-ISSN
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Volume of the periodical
124
Issue of the periodical within the volume
February
Country of publishing house
GB - UNITED KINGDOM
Number of pages
13
Pages from-to
579-591
UT code for WoS article
000451498100049
EID of the result in the Scopus database
2-s2.0-85055444402