Development of a test task for coupled neutronic and thermal-hydraulic analysis of LFR fuel cell

In the absence of operational experience with Generation IV reactors and limited experimental data, developing test tasks is crucial for ensuring the safety and reliability of novel reactor designs. This study presents a test task for coupled neutronic and thermal-hydraulic analysis of a lead-cooled...

Бүрэн тодорхойлолт

Номзүйн дэлгэрэнгүй

Үндсэн зохиолчид:	Maksim Chubarov, Mikhail Zakharov, Ekaterina Bogdanova, Anton Smirnov, Deniel Ouen, Georgy Tikhomirov
Формат:	Artigo
Хэл сонгох:	Inglês
Хэвлэсэн:	Elsevier 2025-11-01
Цуврал:	Nuclear Engineering and Technology
Нөхцлүүд:	CFD Thermal-hydraulics LFR LOGOS software Coupled calculations Reactor benchmark
Онлайн хандалт:	http://www.sciencedirect.com/science/article/pii/S1738573325003316
Шошгууд:	Шошго нэмэх Шошго байхгүй, Энэхүү баримтыг шошголох эхний хүн болох!