Zobrazeno 1 - 10
of 246
pro vyhledávání: '"APR1400"'
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 1, Pp 309-316 (2024)
The U.S. Nuclear Regulatory Commission (NRC) Regulatory Guide (RG) 1.20 provides guidance on the comprehensive vibration assessment program (CVAP) to be performed on reactor internals during pre-operational and startup tests. The purpose of the progr
Externí odkaz:
https://doaj.org/article/b57aed48baa845339c9d817864c32408
Autor:
Mikołaj Oettingen, Juyoul Kim
Publikováno v:
Energies, Vol 17, Iss 19, p 4864 (2024)
The aim of this paper is to present the isotopic changes in nuclear fuel during the first reactor cycle of the Korean Advanced Power Reactor 1400 (APR1400). The neutron transport and burnup calculations were performed using the Monte Carlo continuous
Externí odkaz:
https://doaj.org/article/0e305a4605c94f67a87c4e014fa5f4d7
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 7, Pp 2578-2590 (2023)
In thiswork, a 24-month two-batch fuel management strategy for the APR1400 using LEU + has been investigated, where enrichments of 5.9 and 5.2 w/o are utilized in lieu of the conventional 4–5 w/o UO2 fuel. In addition, an Accident Tolerant Fuel (AT
Externí odkaz:
https://doaj.org/article/1e12566faa64419bae2ad6ce6b0622a9
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 5, Pp 1651-1664 (2023)
It is very difficult to capture the multi-dimensional phenomena such as asymmetric flow and temperature distributions with the one-dimensional (1D) model, obviously, due to its inherent limitation. In order to overcome such a limitation of the 1D rep
Externí odkaz:
https://doaj.org/article/7aaa614c88734f37a204b098445b1a1b
Publikováno v:
Energies, Vol 17, Iss 14, p 3498 (2024)
The KEPCO Nuclear Fuel Company (KNF) has undertaken considerable efforts to improve the KARMA/ASTRA nuclear design code system to meet the increasing demand for high-fidelity core analyses. Through years of effort, the KARMA lattice transport code ba
Externí odkaz:
https://doaj.org/article/81dc6c00320c42178b4deca73e2ef311
Autor:
Tomáš Křeček, Štěpán Foral
Publikováno v:
Acta Polytechnica CTU Proceedings, Vol 44 (2023)
The ALTHAMC12 subchannel code is a new subchannel code developed by the ALVEL company. The code is intended for DNBR safety analyses of the Czech nuclear power plants. In order to validate the code, a code to code comparison with THALES and VIPRE-01
Externí odkaz:
https://doaj.org/article/35f33d3be59b46f5b7905cd1af92e9e5
Akademický článek
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Akademický článek
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Autor:
Muritala A. Amidu, Yacine Addad
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 4, Pp 1508-1515 (2022)
In the present study, the cavity module of the MELCOR code is used for the simulation of molten corium concrete interaction (MCCI) during the late phase of postulated large break loss of coolant (LB-LOCA) accident in the APR1400 reactor design. Using
Externí odkaz:
https://doaj.org/article/e605158642314964a07bd8c09ea756d0
Publikováno v:
Hydrogen, Vol 3, Iss 1, Pp 28-42 (2022)
We performed a hydrogen combustion analysis in the Advanced Power Reactor 1400 MWe (APR1400) containment during a severe accident initiated by a small break loss of coolant accident (SBLOCA) which occurred at a lower part of the cold leg using a mult
Externí odkaz:
https://doaj.org/article/b92fcf5b1de14a31b172ade820753e67