Results 21 to 30 of about 3,020,549 (269)
Conducting local cutout from the surface of the VVER-1000 reactor vessel
Trudy Odesskogo Politehničeskogo Universiteta, 2019 Integrity of the reactor pressure vessel is a critical element in demonstrating the capability of nuclear power plant for operation to at least 80 years.
Олексій Геннадійович Руденко +3 more
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Non-hardening embrittlement mechanism of pressure vessel steel Ni-Cr-Mo-V welds during thermal aging
Advances in Mechanical Engineering, 2020 The mechanical performance of reactor pressure vessel materials is an important factor in the safety and economics of the operation of a nuclear power plant.
Guojun Wei +4 more
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Validation of the Serpent 2 Monte Carlo code for reactor dosimetry applications [PDF]
EPJ Web of Conferences, 2023 The verification and validation (V&V) of the Serpent 2 Monte Carlo code for 3-D reactor dosimetry applications is being carried out at VTT. Two code-to-code computational benchmark cases were calculated by MCNP and Serpent 2. The computational efficiency
Dorval Eric
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Frontiers in Energy Research, 2022 When the large pressurized water reactor in-vessel retention (IVR) system is put into operation, the outer wall of the reactor pressure vessel (RPV) will experience severe temperature fluctuations and be subjected to high internal pressure loads at the ...
Dahuan Zhu +6 more
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Nihon Kikai Gakkai ronbunshu, 2019 The reactor pressure vessel is made of ferritic low alloy steel, which has fracture behaviors that include ductile to brittle transition temperature and decrease of fracture toughness in the beltline region of the reactor pressure vessel steel due to ...
Takatoshi HIROTA, Kentaro YOSHIMOTO
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Analysis of the flow distribution and mixing characteristics in the reactor pressure vessel
Nuclear Engineering and Technology, 2021 The analysis of the fluid flow characteristics in reactor pressure vessel is an important part of the hydraulic design of nuclear power plant, which is related to the structure design of reactor internals, the flow distribution at core inlet and the ...
L.L. Tong, L.Q. Hou, X.W. Cao
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Remote Monitoring of Equipment in Small Modular Reactors
Chemical Engineering Transactions, 2013 Small Modular Reactors (SMR) are being developed by several vendors for remote deployment and for small grid applications. These reactors have the additional advantage of load-following, process heat application, and improved safeguards features.
B. Upadhyaya +3 more
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Validation of RT(T0) for German reactor pressure vessel steels
, 2022 Art. 031405, 6 S.For the introduction of the new reference temperature RTT0 of the ASME Code Cases N-629 and N-631 into the German Standard KTA 3201.2, the applicability of RTT0 was validated by the reevaluation of the existing fracture toughness ...
Keim, E., Siegele, D., Nagel, G.
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Nuclear Engineering and Technology, 2022 This paper presents fracture mechanics analysis results for various cracks located at pressurized water reactor pressure vessel nozzle crotch corners taking into consideration constraint effect. Technical documents such as the ASME B&PV Code, Sec.XI were
Jong-Sung Kim +5 more
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WWER-1000 core loading characteristic influence on irradiation conditions of surveillance specimens and reactor pressure vessel [PDF]
Ядерна фізика та енергетика, 2009 Irradiation conditions of WWER-1000 surveillance specimens and reactor pressure vessel are comparative analyzed for various core loadings. It is proved that the fluences onto specimens don't correlate with ones onto pressure vessel.
V. N. Bukanov +4 more
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