RELAP5 Modeling of a Siphon Break Effect on the Brazilian Multipurpose Reactor by Humberto Vitor Soares, Antonio Belchior Jr., Roberto Longo Freitas

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Thermal study of the modular high-temperature gas-cooled reactor by Antonella Lombardi Costa, Mario Cerrogrande Ramos, Vitor Vasconcelos Araújo Silva, Claubia Pereira, Maria Auxiliadora Fortini Veloso

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Brayton cycle numerical modeling using the RELAP5-3D code, version 4.3.4 by Eduardo Pedroso Longhini, Paulo David de Castro Lobo, Lamartine Nogueira Frutuoso Guimarães, Francisco Antonio Braz Filho, Guilherme Borges Ribeiro

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TRISO fuel thermal simulations in the LS-VHTR by Mario C. Ramos, Maria E. Scari, Antonella Lombardi Costa, Claubia Pereira, Maria A. F. Veloso

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Small break loss of coolant accident of 200 cm² in cold leg of primary loop of Angra2 nuclear power reactor evaluation by EDUARDO MADEIRA BORGES, GAIANÊ SABUNDJIAN

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Simulation of Small-Break Loss-of-Coolant Accident Using the RELAP5 Code with an Improved Wall Drag Partition Model for Bubbly Flow by Young Hwan Lee, Nam Kyu Ryu, Byoung Jae Kim

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Use of the thermo-hydraulic system code RELAP5/MOD3.2 to transient analysis events of the VR-1 reactor by Jakub Mátl, Filip Fejt

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Research on Safety Characteristic of Mobile Gas Cooled Reactor System by MA Xinrong, YANG Yi

Subjects: “…relap5/mod code…”

Thermal hydraulic safety characteristics analysis for the natural circulation primary loop under inclined condition on LFR by Jinting Liu, Jinting Liu, Tingyu Li, Tingyu Li, Tingyu Li, Yang Li, Yang Li, Yang Li, Danna Zhou, Danna Zhou, Danna Zhou, Dajian Yu, Dajian Yu, Dajian Yu

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Analysis of natural circulation characteristics for pool-type fast reactor system by Yufeng Lv, Zhiwei Zhou, Xingmin Liu

Subjects: “…RELAP5 code…”
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