Sensitivity analysis of the MASLWR helical coil steam generator using TRACE-Reference-Cited by-同舟云学术

Sensitivity analysis of the MASLWR helical coil steam generator using TRACE

Published:2011-04 Issue:4 Volume:241 Page:1137-1144
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Mascari F.,Vella G.,Woods B.G.,Welter K.,Pottorf J.,Young E.,Adorni M.,D’auria F.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

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3. Validation of Thermal-Hydraulic Codes for Boron Dilution Transients in the Context of the OECD/SETH and OECD/PKL Projects;Bucalossi,2006

4. Benchmark calculations of pressurizer model for Maanshan nuclear power plant using TRACE code;Cheng;Nuclear Engineering and Design,2009

5. CSNI integral test facility validation matrix for the assessment of thermal-hydraulic codes for LWR LOCA and transients;CSNI,1996

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