Zobrazeno 1 - 10
of 4 506
pro vyhledávání: '"PWR"'
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 10, Pp 4263-4279 (2024)
The small modular PWR (SMPWR) usually adopts integral design. Under severe accident, the system responses are different from those large PWRs. It is necessary to study the severe accident behavior of the SMPWR. A MELCOR model is developed for SMPWR a
Externí odkaz:
https://doaj.org/article/2a291c6726a24fdc8e311b583fef05e4
Autor:
Hyunsik Hong, Jooil Yoon
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 9, Pp 3654-3667 (2024)
Expanding upon the framework of the steady-state pin-by-pin 2D/1D decoupling method, a novel and high-performance pin-by-pin transient calculation method has been introduced. This transient method, consistent to the steady-state formulation, is desig
Externí odkaz:
https://doaj.org/article/ae2135335f664e78831c9778ce7befe0
Autor:
Xinhe Xu, Deng Pan, Kun Zhang, Zhanpeng Lu, Sergio Lozano-Perez, Tongming Cui, Junjie Chen, Shuangyan Li, Maolong Zhang, Tetsuo Shoji
Publikováno v:
Journal of Materials Research and Technology, Vol 31, Iss , Pp 1392-1408 (2024)
The multi-scale chemical composition distribution and microstructure of Alloy 52 M overlay on low alloy steel by hot wire plasma arc cladding (HWPC) were characterized. Stress corrosion cracking (SCC) growth rates were quantified in the dilution zone
Externí odkaz:
https://doaj.org/article/81c877fbe678415aad3c47e06a6f5d21
Autor:
Jaerim Jang, Deokjung Lee
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 6, Pp 2163-2173 (2024)
This study introduces a transient analysis module developed for RAST-V and validates it using the Kalinin-3 benchmark problem. For the benchmark analysis, RAST-V standalone and STREAM/RAST-V calculations were performed. STREAM supplies the few-group
Externí odkaz:
https://doaj.org/article/077e5097c30f41e19d7333485b3017d5
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 3, Pp 907-915 (2024)
Various core designs with multi-batch fuel management (FM) are proposed and optimized for an innovative small modular reactor (iSMR), focusing on enhancing the inherent safety and neutronic performance. To achieve soluble-boron-free (SBF) operation,
Externí odkaz:
https://doaj.org/article/e147c98101234a21ba146e48cdf1aeca
Akademický článek
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Publikováno v:
Nukleonika, Vol 69, Iss 1, Pp 3-12 (2024)
The neutronic characteristics of (Th-233U)O2, (Th-233U)C, and (Th-233U)N have been compared in small long-life pressurized water reactors (PWRs). Neutronic calculations were carried out at 300 MWth, 400 MWth, and 500 MWth with two cladding types: zir
Externí odkaz:
https://doaj.org/article/0e354a67768447d48061bb3ca333319a
Publikováno v:
Crystals, Vol 14, Iss 10, p 846 (2024)
Stainless-steel is extensively utilized in the key structural components of the main equipment in the nuclear island of pressurized water reactor nuclear power plants. The operational experience of nuclear power plants demonstrates that stress corros
Externí odkaz:
https://doaj.org/article/ec9c4fdb849849229ea7d0015bfd3f00
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
Akademický článek
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