Neutron Physical Performance Analysis of Helical Cruciform Fuel Rods Based on Direct Accelerated Geometry Monte Carlo

Springer proceedings in physics 2026

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Authors: Jingqi He, Jiejin Cai
DOI: 10.1007/978-981-95-3449-4_45
Cited by: 0
References: 7

Fields of Study & Subjects

Nuclear reactor physics and engineering Heat transfer and supercritical fluids Nuclear Materials and Properties

Publication details

Journal / source
Springer proceedings in physics
Pages
573–582
Publication date
1 January 2026
Language
EN