Registration Number
0216U001563,
0112U007508
, R & D reports
Title
Development of design and technology production of fuel rods and fuel assemblies for subcritical assembly, conduct their tests in justification of reliability and security
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Head
Krasnorutskyy Volodymyr Semenovich,
Registration Date
24-02-2016
Organization
"Nuclear Fuel Cycle "Science and Technology Establishment National Science Center "Kharkov Institute of Physics and Technology"
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This technical proposal reviewed options of fuel compositions and fuel rod designs taking into account their manufacturing at the technological facilities of NFC STE as the base technological organization with the equipment currently available at the facilities. Fuel rod design Option 1 - which is the simplest to implement and extensively substantiated in terms of its operation in the water-cooled and water-moderated reactor cores (WWER-440 and WWER-1000) by all the parameters reviewed (nuclear, corrosion, thermal physics, availability of materials, process equipment and capabilities to manufacture test samples of fuel, fuel rods, and fuel assemblies by NFC STE specialists) - is a priority for further detailed development for potential use in the sub-critical assembly core. Core nuclear design has demonstrated that the use of this fuel rod option with 5.1% U235 enrichment of the fuel in the 6-rod FA-Kh yields Keff = 0.97850 0.00018 for the sub-critical assembly core with 36 FA-Kh. An attractive option is to use this fuel rod design in the 7-rod FA-Kh with 4.4% U235 enrichment, which is standard for WWER-1000, since in this case Keff of the core loaded with 36 FA-Kh will equal 0.97250 0.00018. Fuel rod design Option 2 is also attractive and recommended for detailed development, since Keff of the core loaded with 36 FA-Kh (with 6 fuel rods) is 0.97539 0.00018. Implementation of this fuel rod design will require additional effort to develop the technology for fuel pellet manufacturing and for U235 concentration control in the fuel pellet. Fuel rod design Option 3 is inferior to the first two due to low maturity of the manufacturing technology, specifically absence of the structural material - SAV-1. Therefore, at the Preliminary Design stage Option 3 will be considered as a backup, implementable provided Ukraine has the technology for manufacturing SAV-1 and the elements based on this alloy.
Product Description
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Абдулаев А.М.о
Бєлаш М.
Ворожко В.
Грицина В.
Данилов А.
Колотилов О.
Красноруцький Володимир Семенович
Кулиш Г.
Слепцов О.
Солдатов С.
Татарінов Володимир Романович
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2020-04-02
