A comprehensive Thermo-hydraulic neutronic and safety analysis of a 100MWth pebble bed reactor core-Reference-Cited by-同舟云学术

A comprehensive Thermo-hydraulic neutronic and safety analysis of a 100MWth pebble bed reactor core

Published:2022-11 Issue: Volume:398 Page:111991
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Boyes W.A,Slabber J.F.M,Boyes D.W

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

Reference11 articles.

1. International Atomic Energy Agency. High Temperature Reactor Fuels and Materials. IAEA-TECDOC-1645, 2010.

2. D. Becker, Ragoß, W. Feltes, and Kohtz “Sicherheitstechnische Nachweise zum Kugelfließen im HTR-Modul,” F&E Abschlußbericht, 1 April 1993.

3. The V.S.O.P. System Present Worth Fuel Cycle Calculation Methods and Codes, KPD;Hansen,1975

4. Internal memoranda reporting on the investigation of pebble flow curves for the AVR. 2009.

5. A. Kadak and M. Bazant “Pebble Flow Experiments for Pebble Bed Reactors,” 2nd International Topical Meeting on High Temperature Reactor Technology, Institute of Nuclear and New Energy Technology, Beijing, China, Sept 22-24, 2004.

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