Critical heat flux in a CANDU end shield – Influence of shielding ball diameter-Reference-Cited by-同舟云学术

Critical heat flux in a CANDU end shield – Influence of shielding ball diameter

Published:2021-10 Issue: Volume: Page:
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Spencer Justin

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference10 articles.

1. Thermal-hydraulic aspects of progression to severe accidents in CANDU reactors;Luxat;Nucl. Technol.,2009

2. Backup and ultimate heat sinks in CANDU reactors for prolonged SBO accidents;Nitheanandan;Nucl. Eng. Technol.,2013

3. Mechanistic modelling of station blackout accidents for a generic 900 MW CANDU plant using the modified RELAP/SCDAPSIM/MOD3.6 code;Zhou;Nucl. Eng. Des.,2018

4. Results of air barbotage experiments simulating two-phase flow in a CANDU end Shield during in-vessel retention;Spencer;ASME J. Nucl. Rad. Sci.,2017

5. Measurement of critical heat flux in a CANDU end shield consisting of a vertical surface abutting a packed bed of steel shielding balls;Spencer;CNL Nucl. Rev.,2017

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