Show simple item record

dc.contributor.authorSARI, Arindi Kumala
dc.contributor.authorSYARIFAH, Ratna Dewi
dc.contributor.authorARKUNDATO, Artoto
dc.date.accessioned2023-05-10T04:07:36Z
dc.date.available2023-05-10T04:07:36Z
dc.date.issued2022-09
dc.identifier.urihttps://repository.unej.ac.id/xmlui/handle/123456789/116021
dc.description.abstractThe research on the design of a pressurized water reactor with a power of 300 MWth and using uranium carbide (UC) fuel has been carried out. Neutronic analysis was carried out using the System Reactor Atomic Code (SRAC) program, which was operated on a set of computers with Linux Operating System (OS), SRAC codes, namely PIU and COREBN. PIU is used to calculate the fuel cell level, and COREBN is used to calculate the reactor core level. The reactor is designed to produce critical conditions. The parameters analyzed in this study were fuel enrichment (U-235), reactor core size, multiplication factor, reactor core configuration, and criticality. This study calculates the neutronic calculation of UC fuel with the addition of Neptunium 237 (Np-237), which aims to reduce the value of the effective multiplication factor (k-eff). Neutronic analysis of UC fuel with critical conditions at Fl = 4.5%, F2 = 5%, F3 = 5.5%, fuel fraction = 55% with the addition of neptunium 237 0.5%.en_US
dc.language.isoenen_US
dc.publisherAIP Conference Proceedingsen_US
dc.subjectPreliminary studyen_US
dc.subject300 MWthen_US
dc.subjectpressurized water reactoren_US
dc.subjectaddition neptunium 237en_US
dc.subjectSRAC-COREBN codeen_US
dc.titlePreliminary Study of 300 MWth Pressurized Water Reactor with Carbide Fuel with Addition Neptunium 237 Using Srac-Corebn Codeen_US
dc.typeArticleen_US


Files in this item

Thumbnail

This item appears in the following Collection(s)

Show simple item record