Sensitivity studies of modular high-temperature gas-cooled reactor postulated accidents-Reference-Cited by-同舟云学术

Sensitivity studies of modular high-temperature gas-cooled reactor postulated accidents

Published:2006-03 Issue:5-6 Volume:236 Page:454-462
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Ball Syd

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

Reference8 articles.

1. Ball, S.J., 1991. MORECA: A Computer Code for Simulating Modular High-Temperature Gas-Cooled Reactor Core Heatup Accidents, NUREG/CR-5712, ORNL/TM-11823. Oak Ridge National Laboratory, Oak Ridge, TN.

2. Ball, S.J., Nypaver, D.J., 1999. GRSAC Users Manual, ORNL/TM-13697. Oak Ridge National Laboratory, Oak Ridge, TN.

3. Cleveland, J.C., Greene, S.R., 1986. Application of THERMIX-KONVEK Code to Accident Analysis of Modular Pebble Bed High Temperature Reactors (HTRs), ORNL/TM-9905. Oak Ridge National Laboratory, Oak Ridge, TN.

4. Modified Zehner-Schlunder models for stagnant thermal conductivity of porous media;Hsu;Int. J. Heat Mass Transfer,1994

5. IAEA, 2001. Heat Transport and Afterheat Removal for Gas Cooled Reactors Under Accident Conditions, IAEA-TECDOC-1163. International Atomic Energy Agency.

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