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Optimization of AHWR core design: neutronics and thermal-hydraulics analysis and calculations
Life Cycle Reliability and Safety Engineering, 2020Advanced Heavy Water Reactor(AHWR) is being designed by BARC for thorium utilisation and demonstrate all aspects of the thorium fuel cycle. The AHWR is a vertical pressure tube type thorium-based reactor cooled by boiling light water and moderated by heavy water. The equilibrium fuel cycle of AHWR is being optimised for a discharge burn-up of 40 GWd/Te
Vishal Bharti +8 more
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Large-scale Monte Carlo neutron transport calculations with thermal hydraulic feedback
Annals of Nuclear Energy, 2015Abstract The Monte Carlo method provides the most accurate description of the particle transport problem. The criticality problem is simulated by following the histories of individual particles without approximating the energy, angle or the coordinate dependence. These calculations are usually done using homogeneous thermal hydraulic conditions. This
Ivanov, A. +3 more
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Neutronics and Thermal Hydraulics Coupled 3-D Calculation of Pressure-Tube Deformation
Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, 2020Abstract Among the various parts in a pressurized heavy-water reactor (PHWR), pressure tubes are of tremendous importance. This is because they withstand extreme both pressure and temperature differences that exist between the Primary Heat Transport System (PHTS) and the moderator.
Eunhyun Ryu +3 more
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Progress on the Development of DAYU3D Code for HTR Thermal-Hydraulic Design and System Analysis
Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory IssuesSystem analysis code is an important tool for thermal-hydraulic design and accident analysis of nuclear reactors. At present, the commonly used system analysis codes for pebble-bed high-temperature gas-cooled reactor (HTR), such as THERMIX and TINTE ...
Haojie Zhang, Ding She, Lei Shi
semanticscholar +1 more source
Quantitative assessment of thermal–hydraulic codes used for heavy water reactor calculations
Nuclear Engineering and Design, 2006Abstract The RD-14M large LOCA test, characterized by a reliable set of experimental data, was selected for an international standard problem exercise (SPE) entitled “Intercomparison and validation of computer codes for thermal–hydraulics safety analyses”.
Andrej Prošek +3 more
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Kerntechnik, 2019
The present paper gathers the main insights obtained during the numerical simulation of a 10 % main steam line break (MSLB) in a generic German PWR KONVOI reactor with the thermal-hydraulic system code ATHLET 3.1A.
E. Pescador, F. Schäfer, S. Kliem
semanticscholar +1 more source
The present paper gathers the main insights obtained during the numerical simulation of a 10 % main steam line break (MSLB) in a generic German PWR KONVOI reactor with the thermal-hydraulic system code ATHLET 3.1A.
E. Pescador, F. Schäfer, S. Kliem
semanticscholar +1 more source
Day 1 Wed, April 10, 2019, 2019
In this work, we present the development of a comprehensive mathematical formulation and reservoir simulator for thermal-hydraulic-mechanical simulation of CO2-EOR processes We adopt the integral finite difference method to simulate coupled thermal ...
Shihao Wang +3 more
semanticscholar +1 more source
In this work, we present the development of a comprehensive mathematical formulation and reservoir simulator for thermal-hydraulic-mechanical simulation of CO2-EOR processes We adopt the integral finite difference method to simulate coupled thermal ...
Shihao Wang +3 more
semanticscholar +1 more source
Influence of Thermal-Hydraulic Model to Fuel Management Core Calculation
2008The integration of neutronic, fuel rod and thermal-hydraulic calculations for both, steady-state core design type of the calculation and for transient and safety analyses, is used to improve the response of Nuclear Power Plants (NPP) both from the point of view of safe and economic plant operation.
Iveković, Ilijana +2 more
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Thermal Engineering, 2019
The results from experimental investigation into hydrodynamics and heat transfer in a two-phase natural circulation loop (NCL) under atmospheric pressure are presented. The experiments were carried out for liquids having essentially different properties: water, ethanol, and perfluorohexane C6F14 (the product trademark is FC-72).
V. V. Yagov +3 more
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The results from experimental investigation into hydrodynamics and heat transfer in a two-phase natural circulation loop (NCL) under atmospheric pressure are presented. The experiments were carried out for liquids having essentially different properties: water, ethanol, and perfluorohexane C6F14 (the product trademark is FC-72).
V. V. Yagov +3 more
openaire +1 more source