Development of Effective Algorithm for Coupled Thermal-Hydraulic–Neutron-Kinetics Analysis of Reactivity Transient-Reference-Cited by-同舟云学术

Development of Effective Algorithm for Coupled Thermal-Hydraulic–Neutron-Kinetics Analysis of Reactivity Transient

Published:2011-11 Issue:2 Volume:176 Page:195-210
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Peltonen Joanna¹,Kozlowski Tomasz¹

Affiliation:

1. Royal Institute of Technology (KTH), Division of Nuclear Power Safety Albanova University Center, Roslagstullsbacken 21, SE-106 91 Stockholm, Sweden

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT11-A13296

Reference11 articles.

1. Investigation of spatial coupling aspects for coupled code application in PWR safety analysis

2. Using the OECD/NRC Pressurized Water Reactor Main Steam Line Break Benchmark to Study Current Numerical and Computational Issues of Coupled Calculations

3. OECD/NRC BWR Turbine Trip Transient Benchmark as a Basis for Comprehensive Qualification and Studying Best-Estimate Coupled Codes

4. “CRISSUE-S-WP2, Neutronics/Thermal-Hydraulics Coupling in LWR Technology: State-of-the-Art Report (REACSOAR),” Organisation for Economic Co-operation and Development/Nuclear Energy Agency (2004).

5. Challenges in coupled thermal–hydraulics and neutronics simulations for LWR safety analysis

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