Results 121 to 130 of about 24,201 (184)
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Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, 2014
Corrosion products deposit on Pressurized Water Reactor (PWR) fuel rod cladding surfaces and can create a number of issues including increased cladding temperature, elevated cladding corrosion, and the precipitation of boron species within the deposits.
W. A. Byers +3 more
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Corrosion products deposit on Pressurized Water Reactor (PWR) fuel rod cladding surfaces and can create a number of issues including increased cladding temperature, elevated cladding corrosion, and the precipitation of boron species within the deposits.
W. A. Byers +3 more
openaire +1 more source
Nuclear Engineering and Design, 1987
Abstract A series of experiments have been performed which help to provide fundamental understanding of the phenomena which are important to the analysis of a PWR pressurizer. The transients considered include insurges to a partially-full tank, outsurges, insurges to a tank with hot walls, empty tank insurges, and combined insurges and outsurges. The
Sang-Nyung Kim, Peter Griffith
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Abstract A series of experiments have been performed which help to provide fundamental understanding of the phenomena which are important to the analysis of a PWR pressurizer. The transients considered include insurges to a partially-full tank, outsurges, insurges to a tank with hot walls, empty tank insurges, and combined insurges and outsurges. The
Sang-Nyung Kim, Peter Griffith
openaire +1 more source
Serpent/SUBCHANFLOW pin-by-pin coupled transient calculations for a PWR minicore
, 2020An increasing interest on the development of highly accurate methodologies in reactor physics has been observed during the last years. The McSAFE high-fidelity project has the objective of moving multiphysics schemes based on Monte Carlo (MC) neutronic ...
D. Ferraro +6 more
semanticscholar +1 more source
, 2020
The detailed thermal-hydraulic phenomena inside the lower plenum of Reactor Pressure Vessel (RPV) in Pressurized Water Reactor (PWR) affect the mass flow rate distributions at core inlet significantly, leading to an impact on the operation safety of ...
Mingjun Wang +6 more
semanticscholar +1 more source
The detailed thermal-hydraulic phenomena inside the lower plenum of Reactor Pressure Vessel (RPV) in Pressurized Water Reactor (PWR) affect the mass flow rate distributions at core inlet significantly, leading to an impact on the operation safety of ...
Mingjun Wang +6 more
semanticscholar +1 more source
Annals of Nuclear Energy, 2019
A Nuclear Power Plant (NPP) is an advanced and complex power generation system that requires a high level of safety to operate. So, when confronted with an anomalous event, such as an accident or a transient scenario, if the event is not correctly ...
M. C. Santos +6 more
semanticscholar +1 more source
A Nuclear Power Plant (NPP) is an advanced and complex power generation system that requires a high level of safety to operate. So, when confronted with an anomalous event, such as an accident or a transient scenario, if the event is not correctly ...
M. C. Santos +6 more
semanticscholar +1 more source
, 2020
Performance of the separation system in the UTSG determines the quality of supplied steam in a nuclear power plant. In the present study, the Eulerian-Lagrangian methodology is applied in a full-scale UTSG separation system of GEN-III China advanced PWR.
Dianqi Fang +8 more
semanticscholar +1 more source
Performance of the separation system in the UTSG determines the quality of supplied steam in a nuclear power plant. In the present study, the Eulerian-Lagrangian methodology is applied in a full-scale UTSG separation system of GEN-III China advanced PWR.
Dianqi Fang +8 more
semanticscholar +1 more source
Energy Policy, 2013
Abstract The construction time of PWRs is studied considering published data about nuclear power plants in the world. For the 268 PWRs in operation in 2010, the mode of the construction time distribution is around 5–6 years, and 80% of the plants were built in less than 120 months.
João M.L. Moreira +2 more
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Abstract The construction time of PWRs is studied considering published data about nuclear power plants in the world. For the 268 PWRs in operation in 2010, the mode of the construction time distribution is around 5–6 years, and 80% of the plants were built in less than 120 months.
João M.L. Moreira +2 more
openaire +1 more source
A three-dimensional PWR-core pin-by-pin analysis code NECP-Bamboo2.0
, 2020A PWR-core pin-by-pin fuel management calculation code system named NECP-Bamboo2.0 has been developed, including the two-dimensional lattice calculation code Bamboo-Lattice2.0 and the three-dimensional steady-state whole-core pin-by-pin calculation code ...
Yunzhao Li +4 more
semanticscholar +1 more source
A Small PWR-Core Physical Calculation Based on PWR-Core Analysis Code CORAL
Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, 2021Abstract Three dimensional PWR-core analysis code CORAL is developed by Wuhan Second Ship Design and Research Institute. This code provides basic functions including three-dimensional power distribution, fine power reconstruction, fuel temperature distribution, critical search, control rod worth, reactivity coefficients, burnup and ...
Wen Yang, Lun Zhou, Junrong Qiu, Yun Tai
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OECD/NRC PWR MOX/UO2 core transient benchmark pin-by-pin solutions using Serpent/SUBCHANFLOW
, 2020In this work, high-fidelity calculations using a recently developed coupled scheme between the Serpent 2 Monte Carlo transport code and the SUBCHANFLOW subchannnel thermal–hydraulic code are done for the well-known full core MOX/UO2 PWR OECD/NRC ...
D. Ferraro +6 more
semanticscholar +1 more source