Design Study of Helium Cooled Fast Reactor with Natural Uranium Fuel Base

Gas Cooled Fast Reactor (GFR) is one of six selected of IV generation reactor. GFR has direct Brayton cycle, uses fast neutron and operates in the high temperature (850oC).This condition gives benefit to produce hydrogen. As we know that hydrogen is the one of promising energy because it cannot prod...

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Main Author: YANTI (NIM 10205068); Pembimbing: Dr. Zaki Su'ud, MERI
Format: Final Project
Language:Indonesia
Online Access:https://digilib.itb.ac.id/gdl/view/13641
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Institution: Institut Teknologi Bandung
Language: Indonesia
id id-itb.:13641
spelling id-itb.:136412017-09-27T11:45:15ZDesign Study of Helium Cooled Fast Reactor with Natural Uranium Fuel Base YANTI (NIM 10205068); Pembimbing: Dr. Zaki Su'ud, MERI Indonesia Final Project INSTITUT TEKNOLOGI BANDUNG https://digilib.itb.ac.id/gdl/view/13641 Gas Cooled Fast Reactor (GFR) is one of six selected of IV generation reactor. GFR has direct Brayton cycle, uses fast neutron and operates in the high temperature (850oC).This condition gives benefit to produce hydrogen. As we know that hydrogen is the one of promising energy because it cannot produce CO2, CO, SO2 and global warming. GFR has high safety, proliferation resistant and economical. In this case, we will burn natural uranium (U-238) for 60 years and put them in 6 regions which have same volume. Hence, in the next 15 year, GFR produce plutonium and this plutonium will be moved from first region to the second region, the fuel from second region is moved to the third region etc. In this experiment, we use GFR with 2400 MWth, helium as coolant and Stainless Steel 316 (SS316) as cladding. In this research, we did some simulation with SRAC, a code developed by the Japan Atomic Energy Research Institute (JAERI), to know the neutron design, and then we will present the result using Microsoft Excel. text
institution Institut Teknologi Bandung
building Institut Teknologi Bandung Library
continent Asia
country Indonesia
Indonesia
content_provider Institut Teknologi Bandung
collection Digital ITB
language Indonesia
description Gas Cooled Fast Reactor (GFR) is one of six selected of IV generation reactor. GFR has direct Brayton cycle, uses fast neutron and operates in the high temperature (850oC).This condition gives benefit to produce hydrogen. As we know that hydrogen is the one of promising energy because it cannot produce CO2, CO, SO2 and global warming. GFR has high safety, proliferation resistant and economical. In this case, we will burn natural uranium (U-238) for 60 years and put them in 6 regions which have same volume. Hence, in the next 15 year, GFR produce plutonium and this plutonium will be moved from first region to the second region, the fuel from second region is moved to the third region etc. In this experiment, we use GFR with 2400 MWth, helium as coolant and Stainless Steel 316 (SS316) as cladding. In this research, we did some simulation with SRAC, a code developed by the Japan Atomic Energy Research Institute (JAERI), to know the neutron design, and then we will present the result using Microsoft Excel.
format Final Project
author YANTI (NIM 10205068); Pembimbing: Dr. Zaki Su'ud, MERI
spellingShingle YANTI (NIM 10205068); Pembimbing: Dr. Zaki Su'ud, MERI
Design Study of Helium Cooled Fast Reactor with Natural Uranium Fuel Base
author_facet YANTI (NIM 10205068); Pembimbing: Dr. Zaki Su'ud, MERI
author_sort YANTI (NIM 10205068); Pembimbing: Dr. Zaki Su'ud, MERI
title Design Study of Helium Cooled Fast Reactor with Natural Uranium Fuel Base
title_short Design Study of Helium Cooled Fast Reactor with Natural Uranium Fuel Base
title_full Design Study of Helium Cooled Fast Reactor with Natural Uranium Fuel Base
title_fullStr Design Study of Helium Cooled Fast Reactor with Natural Uranium Fuel Base
title_full_unstemmed Design Study of Helium Cooled Fast Reactor with Natural Uranium Fuel Base
title_sort design study of helium cooled fast reactor with natural uranium fuel base
url https://digilib.itb.ac.id/gdl/view/13641
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