Results 101 to 110 of about 1,536,451 (138)

RELAP5/MOD3 AP600 problems

open access: yes, 1993
RELAP5/MOD3 is a reactor systems analysis code that has been developed jointly by the US Nuclear Regulatory Commission (USNRC) and a consortium consisting of several of the countries and domestic organizations that were members of the International Code ...
Riemke, R. A.
core  

Alaska Criminal Code Revision Subcommission [PDF]

open access: yes, 1978
As of 1975, Alaska’s criminal laws were based primarily on Oregon criminal statutes as they existed at the close of the nineteenth century, with new statutes added and old statutes amended over the succeeding 75 years by Alaska territorial and state ...
Alaska Criminal Code Revision Subcommission
core  

Workstation experience with RELAP5

open access: yes, 1993
One of the major improvements in the progress from RELAP5/MOD2 to RELAP5/MOD3 was the modification to improve portability. The use of the code was thus extended from the 60 and 64 bit work mainframe computers to 32 bit workstations and PC`s.
Wagner, R. J., Miller, C. S.
core  

RELAP5-3D Code for Supercritical-Pressure Light-Water-Cooled Reactors [PDF]

open access: yes, 2003
The RELAP5-3D computer program has been improved for analysis of supercritical-pressure, light-water-cooled reactors. Several code modifications were implemented to correct code execution failures.
Davis, Cliff Bybee   +2 more
core  

Simulation of the Maanshan Unit 2 full load rejection transient using RELAP5/MOD2 code

open access: yes, 2010
[[abstract]]Maanshan Unit 2's net load rejection transient at full power (power test series No. 2-PAT-51) was investigated and simulated by using RELAP5/MOD2 computer code. The calculated results and their corresponding test data, especially for the time
Pei, B.S.;Yu, G.P.;Kang, J.C.;Hsu, S.S.;Yuann, R.Y.
core  

Restructuring of RELAP5-3D [PDF]

open access: yes, 2005
The RELAP5-3D source code is unstructured with many interwoven logic flow paths. By restructuring the code, it becomes easier to read and understand, which reduces the time and money required for code development, debugging, and maintenance. A structured
Hykes, Joshua, Mesina, George
core  

Coupled Simulation of the NACIE Facility using the RELAP5 Thermal System Code and the CFD Ansys FLUENT Code

open access: yes, 2013
Since the Lead-cooled Fast Reactor (LFR) has been conceptualized in the frame of GEN IV International Forum (GIF), ENEA and Pisa University are strongly involved on the HLM technology development. In the present work is presented the activity carried out
MARTELLI, DANIELE   +4 more
core  

Steam generator identification using piecewise affine model

open access: yesResults 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  

An Integrated RELAP5-3D and Multiphase CFD Code System Utilizing a Semi Implicit Coupling Technique [PDF]

open access: yes, 2001
An integrated code system consisting of RELAP5-3D and a multiphase CFD program has been created through the use of a generic semi-implicit coupling algorithm.
Aumiller, D. L.   +2 more
core  

INVESTIGATION ON TWO-PHASE FLOW INSTABILITIES WITH RELAP5 CODE

open access: yes, 2012
During the operation of any kind of industrial power plant, the stability of the process is of primary importance since it could directly affect the safety on the performance of the system.
NOBILI, MATTEO   +3 more
core  

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