scholarly journals RETRAN: a program for one-dimensional transient thermal--hydraulic analysis of complex fluid flow systems. Volume I. Equations and numerics. Final report. [PWR and BWR]

1977 ◽  
Author(s):  
K. V. Moore ◽  
E. D. Hughes ◽  
J. A. McClure
Keyword(s):  
Fluid Flow ◽  
Final Report ◽  
Hydraulic Analysis ◽  
One Dimensional ◽  
Flow Systems ◽  
Complex Fluid ◽  
Transient Thermal ◽  
Thermal Hydraulic Analysis

Transient Thermal-Hydraulic Analysis of Single Flow Channel Blockage in the JRR-3M 20-MW Research Reactor

2018 ◽  
Vol 204 (1) ◽  
pp. 15-24 ◽  
Author(s):  
Yuchuan Guo ◽  
Guanbo Wang ◽  
Dazhi Qian ◽  
Heng Yu ◽  
Bo Hu ◽  
...  
Keyword(s):  
Research Reactor ◽  
Flow Channel ◽  
Hydraulic Analysis ◽  
Channel Blockage ◽  
Transient Thermal ◽  
Single Flow ◽  
Thermal Hydraulic Analysis

Transient thermal hydraulic analysis of the IAEA 10MW MTR reactor during Loss of Flow Accident to investigate the flow inversion

2013 ◽  
Vol 62 ◽  
pp. 144-152 ◽  
Author(s):  
Omar S. AL-Yahia ◽  
Mohammad A. Albati ◽  
Jonghark Park ◽  
Heetaek Chae ◽  
Daeseong Jo
Keyword(s):  
Hydraulic Analysis ◽  
Transient Thermal ◽  
Thermal Hydraulic Analysis

Pressure Drop Analysis of a Pressure-Channel Type SuperCritical Water-Cooled Reactor

2013 ◽  
Author(s):  
A. Dragunov ◽  
W. Peiman
Keyword(s):  
Pressure Drop ◽  
Supercritical Water ◽  
Nuclear Reactor ◽  
Hydraulic Analysis ◽  
Pressure Drops ◽  
One Dimensional ◽  
Supercritical Water Cooled Reactor ◽  
Thermal Hydraulic Analysis ◽  
Pressure Channel ◽  
Channel Type

Pressure drop calculation and temperature profiles associated with fuel and sheath are important aspects of a nuclear reactor design. The main objective of this paper is to determine the pressure drop in a fuel channel of a SuperCritical Water-cooled Reactor (SCWR) and to calculate the temperature profile of the sheath and the fuel bundles. One-dimensional steady-state thermal-hydraulic analysis was conducted. In this study, the pressure drops due to friction, acceleration, local losses, and gravity were calculated at supercritical conditions.

Preliminary transient thermal-hydraulic analysis for new coated UN and UC fuel options in SCWR

2014 ◽  
Vol 71 ◽  
pp. 152-159 ◽  
Author(s):  
Hao Zhao ◽  
Dahuan Zhu ◽  
Khurrum Saleem Chaudri ◽  
Suizheng Qiu ◽  
Wenxi Tian ◽  
...  
Keyword(s):  
Hydraulic Analysis ◽  
Transient Thermal ◽  
Thermal Hydraulic Analysis

COMPUTATIONAL METHODS: THEIR ADVANTAGES ON TEACHING COMPLEX FLUID FLOW SYSTEMS

2018 ◽  
Author(s):  
Alicia María Tinnirello ◽  
Eduardo Alberto Gago ◽  
Matías Francisco Romero
Keyword(s):  
Fluid Flow ◽  
Computational Methods ◽  
Flow Systems ◽  
Complex Fluid

Transient thermal-hydraulic analysis for reactor cores

1977 ◽  
Vol 44 (1) ◽  
pp. 43-51
Author(s):  
Lun-Shin Yao ◽  
Ivan Catton ◽  
Carl Gazley
Keyword(s):  
Hydraulic Analysis ◽  
Reactor Cores ◽  
Transient Thermal ◽  
Thermal Hydraulic Analysis
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