scholarly journals Application of CUPID for subchannel-scale thermal–hydraulic analysis of pressurized water reactor core under single-phase conditions

2018 ◽  
Vol 50 (1) ◽  
pp. 54-67 ◽  
Author(s):  
Seok Jong Yoon ◽  
Seul Been Kim ◽  
Goon Cherl Park ◽  
Han Young Yoon ◽  
Hyoung Kyu Cho
Keyword(s):  
Single Phase ◽  
Reactor Core ◽  
Pressurized Water Reactor ◽  
Hydraulic Analysis ◽  
Pressurized Water ◽  
Water Reactor ◽  
Thermal Hydraulic Analysis

scholarly journals A RELAP5 model for the thermal-hydraulic analysis of a typical pressurized water reactor

2010 ◽  
Vol 14 (1) ◽  
pp. 79-88 ◽  
Author(s):  
Said Agamy ◽  
Adul Metwally ◽  
Mohammad Al-Ramady ◽  
Sayed Elaraby
Keyword(s):  
Power Plants ◽  
Natural Circulation ◽  
Reactor Core ◽  
Cooling Water ◽  
Pressurized Water Reactor ◽  
Hydraulic Analysis ◽  
Pressurized Water ◽  
Water Reactor ◽  
Operator Action ◽  
Thermal Hydraulic Analysis

This study describes a RELAP5 computer code for thermal-hydraulic analysis of a typical pressurized water reactor. RELAP5 is used to calculate the thermal hydraulic characteristics of the reactor core and the primary loop under steady-state and hypothetical accidents conditions. New designs of nuclear power plants are directed to increase safety by many methods like reducing the dependence on active parts (such as safety pumps, fans, and diesel generators ) and replacing them with passive features (such as gravity draining of cooling water from tanks, and natural circulation of water and air). In this work, high and medium pressure injection pumps are replaced by passive injection components. Different break sizes in cold leg pipe are simulated to analyze to what degree the plant is safe (without any operator action) by using only these passive components. Also station blackout accident is simulated and the time response of operator action has been discussed.

CFD Analysis of the Coolant Mixing within the Upper Plenum of a Pressurized Water Reactor (PWR)

2013 ◽  
Vol 444-445 ◽  
pp. 411-415 ◽  
Author(s):  
Fu Cheng Zhang ◽  
Shen Gen Tan ◽  
Xun Hao Zheng ◽  
Jun Chen
Keyword(s):  
Temperature Distribution ◽  
Fluid Dynamic ◽  
Characteristic Temperature ◽  
Reactor Core ◽  
Flow Distribution ◽  
Sensitivity Study ◽  
Cfd Model ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor

In this study, a Computational Fluid Dynamic (CFD) model is established to obtain the 3-D flow characteristic, temperature distribution of the pressurized water reactor (PWR) upper plenum and hot-legs. In the CFD model, the flow domain includes the upper plenum, the 61 control rod guide tubes, the 40 support columns, the three hot-legs. The inlet boundary located at the exit of the reactor core and the outlet boundary is set at the hot-leg pipes several meters away from upper plenum. The temperature and flow distribution at the inlet boundary are given by sub-channel codes. The computational mesh used in the present work is polyhedron element and a mesh sensitivity study is performed. The RANS equations for incompressible flow is solved with a Realizable k-ε turbulence model using the commercial CFD code STAR-CCM+. The analysis results show that the flow field of the upper plenum is very complex and the temperature distribution at inlet boundary have significant impact to the coolant mixing in the upper plenum as well as the hot-legs. The detailed coolant mixing patterns are important references to design the reactor core fuel management and the internal structure in upper plenum.

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