Results 91 to 100 of about 2,651,698 (166)

International Code Assessment and Applications Program: Summary of code assessment studies concerning RELAP5/MOD2, RELAP5/MOD3, and TRAC-B. International Agreement Report [PDF]

, 1993
Members of the International Code Assessment Program (ICAP) have assessed the US Nuclear Regulatory Commission (USNRC) advanced thermal-hydraulic codes over the past few years in a concerted effort to identify deficiencies, to define user guidelines, and to determine the state of each code. The results of sixty-two code assessment reviews, conducted at
openaire   +2 more sources

Computation of Gap Conductance in Different Fuel Assemblies in VVER-1000 Type Reactors [PDF]

مجله علوم و فنون هسته‌ای, 2011
In this paper, a calculation for fresh fuels gap conductance at different axial lengths of fuel assemblies of the VVER-1000 type reactors has been made using two models of Calza-Bini and Relap5.
M Rahgoshay, KH Shokri
doaj  

Analysis of natural circulation characteristics for pool-type fast reactor system

International Journal of Advanced Nuclear Reactor Design and Technology
In the inherent safety design of the pool-type fast reactor, when the normal heat transfer routine of the primary system is lost during accident conditions, the residual heat of the reactor core is transferred to the ultimate heat sink through the ...
Yufeng Lv, Zhiwei Zhou, Xingmin Liu
doaj   +1 more source

Steam generator identification using piecewise affine model

Results in Nonlinear Analysis, 2019
The role of steam generators in power plants is to remove the thermal power produced in the first cycle and provide the turbine intake steam. Controlling the steam generator water level has an important role in preventing unwanted turbine trips and ...
Samaneh Sadat Sajjadi, Amin Jajarmi, Ahamad Hajipour
doaj  

Numerical simulation of heat dissipation characteristics in PWR high-pressure coolant pipes during cold shutdown. [PDF]

Sci Rep
Tang F, Wang W, Luo Y, Chen Y, Yan B, Liu S.   +5 more
europepmc   +1 more source

Preliminary risk assessment of in-vessel leakage accident in ITER. [PDF]

Sci Rep
Duan Q, Fang X, Chen S, Xie H, Wang C, Wang D.   +5 more
europepmc   +1 more source

An integrated method for the leakage fault mode diagnosis and life prediction of the reactor coolant pump. [PDF]

PLoS One
Shao Y, Kang R, Fu J, Liu J.
europepmc   +1 more source

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Molten salt mixture properties in RELAP5 code for thermodynamic solar applications

International Journal of Thermal Sciences, 2008
Abstract Ongoing research on innovative and environmentally sustainable systems for energy production, as an alternative to the traditional sources, led ENEA to investigate high temperature heat generation by solar power and the subsequent energy collection and storage.
R. Ferri, A. Cammi, D. Mazzei
semanticscholar   +4 more sources

An investigation on flashing-induced natural circulation instabilities based on RELAP5 code

Annals of Nuclear Energy, 2018
In this investigation, flow instability experiments carried out in a natural circulation loop at the low-pressure condition. Based on experiment data, the RELAP5 code was adopted in the analysis. The objective of this investigation is to get insight into
Qiang Wang, P. Gao, Xianbing Chen, Zhongyi Wang, Ying Huang   +4 more
semanticscholar   +3 more sources

Preliminary study of coupling CFD code FLUENT and system code RELAP5

Annals of Nuclear Energy, 2014
Abstract The present paper discusses a coupling strategy of the 3D (three-dimensional) computational fluid dynamics (CFD) code ANSYS-FLUENT with the best estimate 1D (one-dimensional) thermal–hydraulic system code RELAP5/MOD3.1. Preliminarily, by using DLL (Dynamic Link Library) technology and FLUENT UDF (User Defined Functions), an explicit coupling
Wei Li, Xiaoli Wu, Dalin Zhang, Guanghui Su, Wenxi Tian, Suizheng Qiu   +5 more
openaire   +3 more sources