Analysis for the Effect of Spatial Discretization Method on AP1000 Reactor Pressure Vessel Fluence Calculation
Maintaining the structural integrity of the reactor pressure vessel (RPV) is a critical concern related to the safe operation of nuclear power plants. To estimate the structural integrity over the designed lifetime and to support analyses for a potential plant life extension, an accurate calculation...
Main Authors: | Junxiao Zheng, Bin Zhang, Shengchun Shi, Yixue Chen |
---|---|
Format: | Article |
Language: | English |
Published: |
Hindawi Limited
2016-01-01
|
Series: | Science and Technology of Nuclear Installations |
Online Access: | http://dx.doi.org/10.1155/2016/3461290 |
Similar Items
-
Validation of 3D Code KATRIN For Fast Neutron Fluence Calculation of VVER-1000 Reactor Pressure Vessel by Ex-Vessel Measurements and Surveillance Specimens Results
by: Dzhalandinov A., et al.
Published: (2016-01-01) -
PIN POWER CALCULATION SCHEME FOR REACTOR PRESSURE VESSEL FAST NEUTRON FLUENCE ESTIMATION
by: Brovchenko Mariya, et al.
Published: (2021-01-01) -
Methodology of Fuel Burn Up Fitting in VVER-1000 Reactor Core by Using New Ex-Vessel Neutron Dosimetry and In-Core Measurements and its Application for Routine Reactor Pressure Vessel Fluence Calculations
by: Borodkin Pavel, et al.
Published: (2016-01-01) -
Transformation of pressurized water reactor AP1000 to fuzzy graph
by: Ashaari, Azmirul, et al.
Published: (2018) -
Relap 5 Analysis of AP1000 Pressured Water Reactor Containment
by: Tseng, Shao-Wei, et al.
Published: (2011)