Criticality and rod worth analysis of the DNRR research reactor using the SRAC and MCNP5 codes-Reference-Cited by-同舟云学术

Criticality and rod worth analysis of the DNRR research reactor using the SRAC and MCNP5 codes

Published:2019-03 Issue: Volume:343 Page:197-209
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Do Quang Binh,Phan Giang T.T.,Nguyen Kien-Cuong,Ngo Quang Huy,Tran Hoai-Nam

Funder

NAIS

National Foundation for Science and Technology Development

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

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5. Fuel burnup analysis of the TRIGA Mark II reactor at the University of Pavia;Chiesa;Ann. Nucl. Energy,2016

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