Development of A Coupled Neutron Kinetics And Thermal Hydraulics Code With 3-D Two Group Neutron Kinetics Solver and OpenFOAM by Adding Feedback of Coolant Temperature in Calculation of Cross Section Using DRAGON for Pressurized Heavy Water Reactor

Main Author: jha, alok
Format: Dataset
Terbitan: Mendeley , 2018
Subjects:
Online Access: https:/data.mendeley.com/datasets/2nz429tdzb

Internet

https:/data.mendeley.com/datasets/2nz429tdzb

Lokasi

Koleksi Artikel mulono
Gedung Teknologi Pangan UNISI
Institusi Universitas Islam Indragiri
Kota INDRAGIRI HILIR
Provinsi RIAU
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