Decay Heat Uncertainty Analysis for VVER Spent Nuclear Fuel
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21730%2F25%3A00386159" target="_blank" >RIV/68407700:21730/25:00386159 - isvavai.cz</a>
Result on the web
<a href="https://doi.org/10.1115/1.4068690" target="_blank" >https://doi.org/10.1115/1.4068690</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1115/1.4068690" target="_blank" >10.1115/1.4068690</a>
Alternative languages
Result language
angličtina
Original language name
Decay Heat Uncertainty Analysis for VVER Spent Nuclear Fuel
Original language description
Total Monte Carlo (TMC) extends the Monte Carlo method, using stochastic techniques and random sampling to solve the Boltzmann transport equation in spent nuclear fuel (SNF) depletion analysis. TMC evaluates the impact of uncertainties in nuclear data, such as cross sections and fission product yields, on SNF characteristics, focusing on decay heat, which is crucial for SNF handling and management. TMC generates random nuclear data variations within uncertainty ranges for Monte Carlo simulations, resulting in outcome distributions (e.g., decay heat) that reflect real-world behavior uncertainties. The uncertainty analysis examined a standard VVER-440 nuclear fuel. Using the serpent 2 code and referencing the endf/b-viii.0 and tendl nuclear data libraries, the study focused on the impact of cross sections and fission product yield nuclear data uncertainty on the decay heat of a standard VVER-440 nuclear fuel. The time frame chosen for both post-reactor shutdown and long-term for spent fuel cask loading is chosen, providing a comprehensive view of the nuclear fuel cycle.
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/TN02000012" target="_blank" >TN02000012: Center of Advanced Nuclear Technology II</a><br>
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Others
Publication year
2025
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Name of the periodical
Journal of Nuclear Engineering and Radiation Science
ISSN
2332-8983
e-ISSN
2332-8975
Volume of the periodical
11
Issue of the periodical within the volume
4
Country of publishing house
US - UNITED STATES
Number of pages
3
Pages from-to
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UT code for WoS article
001572068100001
EID of the result in the Scopus database
2-s2.0-105012563929