Zobrazeno 1 - 10
of 12
pro vyhledávání: '"Jiří Závorka"'
Publikováno v:
Kerntechnik. 85:336-340
This work deals with the updated reference solution of the Full-Core VVER-440 PK-3+ benchmark which is based on the extended calculation benchmark from 2018. [1] The modification consists of a new type of fuel assembly with PK-3 design in the loading
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f3b60d1b9e55ad1412666d9f2cfdafbb
https://doi.org/10.3139/124.200020
https://doi.org/10.3139/124.200020
The paper describes the development, validation, and use of UWB1 code intended for fast calculation of nuclear fuel depletion in burnable absorber research. The degree of effectiveness of burnable absorbers in the form of natural abundance elements,
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::e1f2acfaf7076528c1de79c0f140c5bf
http://hdl.handle.net/11025/36548
http://hdl.handle.net/11025/36548
Autor:
Daniel Sprinzl, Václav Krysl, Pavel Mikoláš, Jiří Závorka, Jan Tímr, Yurii Bilodid, Emese Temesvari, István Pós, Yuriy Kalinin, Anna Shcherenko, Sergey Aleshin, Tamer Bahadir
Publikováno v:
Kerntechnik 85(2020)4, 231-244
This work deals with the \Full-Core" VVER-1000 calculation benchmark which was proposed on the 26th Symposium of AER [1]. Recently, the calculation benchmarks \Full-Core" VVER-440 [2] and its extension [3] have been introduced in the AER community wi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::2a3e6b65f7e1b0059b9119df320929b5
http://hdl.handle.net/11025/42217
http://hdl.handle.net/11025/42217
Autor:
P. Mikoláš, J. Vimpel, V. Krýsl, A. I. Shcherenko, J. Švarný, D. Sprinzl, R. Vočka, I. Pós, I. Panka, Jiří Závorka, K. Y. Kurakin
Publikováno v:
Kerntechnik. 83:282-293
This work deals with “Full-Core” VVER-440 extended calculation benchmark which was proposed on the 24th Symposium of AER in October 2014 [2]. This benchmark is based on calculation benchmark defined by ŠKODA JS a.s. on the 21st Symposium of AER
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::42e37d8d212679ec39f5615e7f40930f
https://doi.org/10.3139/124.110901
https://doi.org/10.3139/124.110901
Publikováno v:
Scopus-Elsevier
Nowadays Gen. IV reactors are attracting more attention, and so the same attention should be given to the safety and security requirements of these reactors. One of the most critical safety criteria is connected to the control of the chain reaction a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::d3e75521b7c69afa9e06f7427574f9d0
http://hdl.handle.net/11025/36549
http://hdl.handle.net/11025/36549
Publikováno v:
EPJ Web of Conferences, Vol 247, p 17003 (2021)
Higher enrichment of nuclear fuel along the manufacturing limit of boron content in steel and aluminum alloys represents a significant challenge in designing spent fuel transport and storage facilities. One possible solution for spent fuel pools and
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::eb5b4105f4fcc80dd798e53d8711bba4
https://doi.org/10.1051/epjconf/202124717003
https://doi.org/10.1051/epjconf/202124717003
Autor:
P. Haroková, Jana Jiřičková, Martin Lovecký, Kristýna Klímek Gincelová, Jiří Závorka, Vladimír Smutný
Publikováno v:
Annals of Nuclear Energy. 148:107736
The latest ENDF/B nuclear data library released in 2018 is the result of a new international approach to develop evaluated nuclear data for general purpose applications. In order to use the latest ENDF/B-VIII.0 nuclear data library in safety analyses
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::affe94a3d9af59714af294a97ca1f1a5
https://doi.org/10.1016/j.anucene.2020.107736
https://doi.org/10.1016/j.anucene.2020.107736
Publikováno v:
Volume 9: Student Paper Competition.
The research of burnable absorber (BA) is a very important issue, due to BA influence on regulation and control of reactivity in the reactor. Burnable absorbers compensate initial excess reactivity in the reactor and thus allow longer fuel cycle with
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1cc3adb995113f16554455f67948bcc7
https://doi.org/10.1115/icone26-81215
https://doi.org/10.1115/icone26-81215
Geometry models for Monte Carlo transport codes have been using standard constructive solid geometry (CSG). The standard approach is using analytical equations for defining surfaces from which spatial cells are constructed. Both union and intersectio
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::d905cb48a113701d90f13631a963ccaa
http://hdl.handle.net/11025/33833
http://hdl.handle.net/11025/33833
Autor:
Radek Škoda, Jiří Závorka
Publikováno v:
Volume 5: Student Paper Competition.
The problem with higher nuclear fuel enrichment is its high initial reactivity. It has a negative effect on the peaking factor, which is one of the license conditions. The second major problem is the ability to control the reactivity of the reactor,
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fc38873deed09c6cc512e2cfd8d10959
https://doi.org/10.1115/icone24-60302
https://doi.org/10.1115/icone24-60302