Autor: |
Krása Antonín, Kochetkov Anatoly, Baeten Peter, Vittiglio Guido, Wagemans Jan, Bécares Vicente |
Jazyk: |
angličtina |
Rok vydání: |
2017 |
Předmět: |
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Zdroj: |
EPJ Web of Conferences, Vol 146, p 06019 (2017) |
Druh dokumentu: |
article |
ISSN: |
2100-014X |
DOI: |
10.1051/epjconf/201714606019 |
Popis: |
VENUS-F is a fast, zero-power reactor with 30% wt. metallic uranium fuel and solid lead as coolant simulator. It serves as a mockup of the MYRRHA reactor core. This paper describes integral experiments performed in two critical VENUS-F core configurations (with and without graphite reflector). Discrepancies between experiments and Monte Carlo calculations (MCNP5) of keff, fission rate spatial distribution and reactivity effects (lead void and fuel Doppler) depending on a nuclear data library used (JENDL-4.0, ENDF-B-VII.1, JEFF-3.1.2, 3.2, 3.3T2) are presented. |
Databáze: |
Directory of Open Access Journals |
Externí odkaz: |
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