Scaling in nuclear reactor system thermal-hydraulics-Reference-Cited by-同舟云学术

Scaling in nuclear reactor system thermal-hydraulics

Published:2010-10 Issue:10 Volume:240 Page:3267-3293
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

D’Auria F.,Galassi G.M.

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

Reference164 articles.

1. Maintenance of European LWR Integral System Tests Thermal-Hydraulic Databases. European Commission Report CERTA/SC/D6 EUR 19937;Addabbo,2001

2. Fluid to fluid modeling of critical heat flux: a compensated distortion model;Ahmad;Int. J. Heat Mass Transfer,1973

3. User effects on the thermal-hydraulic transient system codes calculations;Aksan;Nuclear Engineering and Design,1993

4. International training program for thermal-hydraulic system code users;Aksan,2000

5. Simulation of conduction heat transfer in the structures of a nuclear plant;Ambrosini,1985

Cited by 73 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Scaling in nuclear thermal hydraulics: Advances, applications and future perspectives in Spain;Nuclear Engineering and Design;2024-09

2. Scaling methodologies and similarity analysis for thermal hydraulics test facility development for water-cooled small modular reactor;Nuclear Engineering and Design;2024-08

3. Validation of codes for modeling and simulation of nuclear power plants: A review;Nuclear Engineering and Design;2024-05

4. Full scope scaling analysis and recommendations for PWR SGTR scenarios;Nuclear Engineering and Design;2024-03

5. OECD/NEA/CSNI state-of-the-art report on scaling in system thermal-hydraulics applications to nuclear reactor safety and design (The S-SOAR);Nuclear Engineering and Design;2024-01