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Neutronic and thermohydraulic blanket analysis for hybrid fusion–fission reactor during operation

Document Type

Article

Author

Bedenko, S.V.; Lutsik, I.O.; Polozkov, S.D.; Prikhodko, V.V.; Matyushin, A.A.; Shmakov, V.M.; Modestov, D.G.; Vega–Carrillo, H.R.

Source

In: Nuclear Engineering and Technology. (Nuclear Engineering and Technology, July 2023, 55(7):2678-2686)

Subject

Language

English

ISSN

2234358X
17385733

Online Access

Full Text (ScienceDirect 종량제) Full Text (ScienceDirect O/A) Open Access (EBSCO) Web of Science JCR 저널정보 Scopus Find it@PNU

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