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Gas-cooled reactor thermal hydraulic analyses with MELCOR

  • Published:2015-11 Issue: Volume:85 Page:404-414
  • ISSN:0149-1970
  • Container-title:Progress in Nuclear Energy
  • language:en
  • Short-container-title:Progress in Nuclear Energy

Author:

Beeny Bradley,Vierow Karen

Funder

Nuclear Regulatory Commission

Sandia National Laboratories

Publisher

Elsevier BV

Subject

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

Reference4 articles.

1. Thermal Hydraulic Analysis of a Reduced Scale High Temperature Gas-cooled Reactor Test Facility and its Prototype with MELCOR;Beeny,2012

2. Pre-application Safety Evaluation Report for the Modular High Temperature Gas-cooled Reactor (MHTGR);Donohew,1995

3. MELCOR Computer Code Manuals;Gauntt,2008

4. Graphite Design Handbook;Ho,1991

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