A coupled neutronic/thermal–hydraulic module for the transient analysis of VVER-1000 reactor during reactivity insertion accidents-Reference-Cited by-同舟云学术

A coupled neutronic/thermal–hydraulic module for the transient analysis of VVER-1000 reactor during reactivity insertion accidents

Published:2020-03 Issue: Volume:121 Page:103249
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Ajami Mona,Zangian Mahdi^ORCID,Minuchehr Abdolhamid,Zolfaghari Ahmadreza

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

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3. COBRA-EN: an Upgraded Version of the COBRA-3C/MIT Code for Thermal–Hydraulic Transient Analysis of Light Water Reactor Fuel Assemblies and Cores;Basile,1999

4. PARCS n2.7 US NRC Core Neutronics Simulator;Downar,2006

5. Nuclear Reactor Analysis;Duderstadt,1976

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