A Study on the Application of CRUDTRAN Code in Primary Systems of Domestic Pressurized Heavy-Water Reactors for Prediction of Radiation Source Term-Reference-Cited by-同舟云学术

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A Study on the Application of CRUDTRAN Code in Primary Systems of Domestic Pressurized Heavy-Water Reactors for Prediction of Radiation Source Term

Published:2017-04 Issue:3 Volume:49 Page:638-644
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Song Jong Soon^ORCID,Cho Hoon Jo^ORCID,Jung Min Young^ORCID,Lee Sang Heon^ORCID

Funder

Ministry of Science, ICT and Future Planning

Korean National research Foundation

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference7 articles.

1. Modeling of transport of radioactive substances in the primary circuit of water-cooled reactors;IAEA,2012

2. Nuclear Materials;Hong,2012

3. Radioactive Waste Management of Nuclear Power Plant;Song,2015

4. An activity transport model for CANDU based on iron transport in the primary coolant;Burrill,1998

5. The accelerated corrosion of CANDU outlet feeders—observations, possible mechanisms and potential remedies;Lister,1997

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4. Design of a Portable Phoswich Detector for Simultaneous α, β, and γ Identification;IEEE Transactions on Nuclear Science;2022-12

5. Research and Development of Source Term Activity Reconstruction System Based on Deep Learning;Annals of Nuclear Energy;2022-09

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