Estimation of safety parameters of equilibrium cycle of Indian Pressurized Water Reactor (IPWR)

2020 ◽  
Vol 9 (2) ◽  
pp. 129-134
Author(s):  
Devesh Raj ◽  
Umasankari Kannan
Keyword(s):  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor ◽  
Safety Parameters

Prediction of safety parameters of pressurized water reactor based on feature fusion neural network

2022 ◽  
Vol 166 ◽  
pp. 108803
Author(s):  
Yinghao Chen ◽  
Dongdong Wang ◽  
Cao Kai ◽  
Cuijie Pan ◽  
Yayun Yu ◽  
...  
Keyword(s):  
Neural Network ◽  
Feature Fusion ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor ◽  
Safety Parameters

scholarly journals Neutronic analysis of fuel pin design for the long-life core in a pressurized water reactor

2021 ◽  
Vol 11 (1) ◽  
pp. 9-15
Author(s):  
Van Khanh Hoang ◽  
Vinh Thanh Tran ◽  
Dinh Hung Cao ◽  
Viet Ha Pham Nhu
Keyword(s):  
Coolant Temperature ◽  
Pressurized Water Reactor ◽  
Fuel Temperature ◽  
Pressurized Water ◽  
Water Reactor ◽  
Fuel Model ◽  
Reactivity Coefficients ◽  
Fuel Pin ◽  
Safety Parameters ◽  
Long Life

This work presents the neutronic analysis of fuel design for a long-life core in a pressurized water reactor (PWR). In order to achieve a high burnup, a high enrichment U-235 is traditionally considered without special constraints against proliferation. To counter the excess reactivity, Erbium was selected as a burnable poison due to its good depletion performance. Calculations based on a standard fuel model were carried out for the PWR type core using SRAC code system. A parametric study was performed to quantify the neutronically achievable burnup at a number of enrichment levels and for a numerous geometries covering a wide design space of lattice pitch. The fuel temperature and coolant temperature reactivity coefficients as well as the small and large void reactivity coefficients are also investigated. It was found that it is possible to achieve sufficient criticality up to 100 GWd/tHM burnup without compromising the safety parameters.

A Space–Time-Dependent Study of Control Rods Withdrawal in a Large-Size Pressurized Water Reactor

2016 ◽  
Vol 3 (1) ◽  
Author(s):  
Sanjeev Kumar ◽  
K. Obaidurrahman ◽  
Om Pal Singh ◽  
Prabhat Munshi
Keyword(s):  
Neutron Flux ◽  
Control Systems ◽  
Nucleate Boiling ◽  
Space Time ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor ◽  
Large Size ◽  
Safety Parameters ◽  
Control Rods

This work focuses on the safety analysis of a typical pressurized water reactor (PWR) for reactivity-initiated transients. These transients result from withdrawal of six sets of groups of control rods that may occur under control systems or other faults. NEA/OECD PWR benchmark is considered for the study. A 3D space–time kinetics code, “TRIKIN” (neutronic and thermal-hydraulics coupled code) is used to account for local changes in the neutron flux. These local changes in the neutron flux affect the total reactivity, local power, and temperature distribution. The safety parameters are the usual 3D radial power distribution, flux tilt, axial heat flux for the peak channel, and radial peak central line temperature profiles over the horizontal plane. These safety parameters studied in the incident progression up to reactor SCRAM level. The minimum departure from the nucleate boiling ratio (MDNBR) has been investigated quantitatively for all six cases. The case that gives maximum drop in MDNBR at SCRAM level is identified and its consequences are discussed. The study is of high importance in revealing the importance of grouping of control rods’ configurations, providing insight in developing strategy for designing the configuration and reactivity worth of groups of control rods and local/global reactor control systems for large-size PWRs.

Investigation on primary side oriented accident management measures in a hypothetical station blackout scenario for a VVER-1000 pressurized water reactor

Kerntechnik ◽  
2010 ◽  
Vol 75 (1-2) ◽  
pp. 12-19 ◽  
Author(s):  
P. Tusheva ◽  
F. Schäfer ◽  
N. Reinke ◽  
E. Altstadt ◽  
U. Rohde ◽  
...  
Keyword(s):  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor ◽  
Management Measures ◽  
Accident Management ◽  
Station Blackout

Highly Accurate Method for the Solution of Flow Coastdown in Pressurized Water Reactor

2019 ◽  
Vol 205 (9) ◽  
pp. 1175-1184
Author(s):  
Sadia Khalid ◽  
Idrees Ahmad ◽  
Awais Zahur
Keyword(s):  
Accurate Method ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor
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