A comparison of three algorithms applied in thermal-hydraulics and neutronics codes coupling for lbe-cooled fast reactor
Author:
Funder
National Natural Science Foundation of China
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference23 articles.
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3. Bonifetto, R, Dulla, S, Ravetto, P, et al. A full-core coupled neutronic/thermal-hydraulic code for the modeling of lead-cooled nuclear fast reactors[J]. Nuclear Engineering & Design, 261(Complete):85-94.
4. L. Chandra F. Roelofs Inter fuel-assembly thermal-hydraulics for the ELSY square open reactor core design[J] Nuclear Engineering and Design 240(10):p.3009-3019 2010
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