STUDY ON NEUTRONIC OF VERY SMALL PB - BI COOLED NO-ONSITE REFUELLING NUCLEAR POWER REACTOR (VSPINNOR)

The technology of nuclear reactors increase rapidly, particularly in the development of Nuclear Power Plant (NPP). Utilization of nuclear energy in power generation system through a phase of regeneration from generation I, II, III to now and IV generation in the future will come with the design opti...

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Main Author: ARIANTO (NIM. 20211015); Pembimbing : Prof. Dr.Eng. Zaki Su'ud, FAJAR
Format: Theses
Language:Indonesia
Online Access:https://digilib.itb.ac.id/gdl/view/20093
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Institution: Institut Teknologi Bandung
Language: Indonesia
id id-itb.:20093
spelling id-itb.:200932017-09-27T14:40:52ZSTUDY ON NEUTRONIC OF VERY SMALL PB - BI COOLED NO-ONSITE REFUELLING NUCLEAR POWER REACTOR (VSPINNOR) ARIANTO (NIM. 20211015); Pembimbing : Prof. Dr.Eng. Zaki Su'ud, FAJAR Indonesia Theses INSTITUT TEKNOLOGI BANDUNG https://digilib.itb.ac.id/gdl/view/20093 The technology of nuclear reactors increase rapidly, particularly in the development of Nuclear Power Plant (NPP). Utilization of nuclear energy in power generation system through a phase of regeneration from generation I, II, III to now and IV generation in the future will come with the design optimization system, power, fuel management, passive safety, and non-proliferation. In this research has been conducted study on neutronik of Very Small Pb-Bi No-Onsite Refuelling Cooled Nuclear Reactor (VSPINNOR) with Uranium nitride fuel using <br /> <br /> <br /> Monte Carlo N-Particle eXtended (MCNPX) program. The VSPINNOR dimension is 100x100cm with cylinder radial balance terrace geometry which is divided into three regions, which is the outer portion with the highest enrichment, the deeper parts with lower enrichment, and most in the area without fuel enrichment. VSPINNOR fast reactor was operated for 10 years with variations of 10-13% fuel enrichment on Ist and IInd models. Neutronic parameters were analyzed in this study are the level of burnup, neutron flux distribution, effective multiplication factor, power density, the value of the average excess reactivity and power peaking factor on the optimum VSPINNOR design. Neutronic calculation results and analysis show that a design can be optimized a design of VSPINNOR fast reactor for the IInd model of terrace at the thermal power output of 300 MWt with 60% fuel fraction and fuel enrichment from 10.5 to 12.5%. At the optimum design of VSPINNOR terrace, burnup value obtained 17.63% HM (heavy metal), the pattern of distribution of neutron fairly evenly, the average power density of 363.56 watts/cc, and power peaking factor 1.21 with the value of the average excess reactivity <1%. 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 The technology of nuclear reactors increase rapidly, particularly in the development of Nuclear Power Plant (NPP). Utilization of nuclear energy in power generation system through a phase of regeneration from generation I, II, III to now and IV generation in the future will come with the design optimization system, power, fuel management, passive safety, and non-proliferation. In this research has been conducted study on neutronik of Very Small Pb-Bi No-Onsite Refuelling Cooled Nuclear Reactor (VSPINNOR) with Uranium nitride fuel using <br /> <br /> <br /> Monte Carlo N-Particle eXtended (MCNPX) program. The VSPINNOR dimension is 100x100cm with cylinder radial balance terrace geometry which is divided into three regions, which is the outer portion with the highest enrichment, the deeper parts with lower enrichment, and most in the area without fuel enrichment. VSPINNOR fast reactor was operated for 10 years with variations of 10-13% fuel enrichment on Ist and IInd models. Neutronic parameters were analyzed in this study are the level of burnup, neutron flux distribution, effective multiplication factor, power density, the value of the average excess reactivity and power peaking factor on the optimum VSPINNOR design. Neutronic calculation results and analysis show that a design can be optimized a design of VSPINNOR fast reactor for the IInd model of terrace at the thermal power output of 300 MWt with 60% fuel fraction and fuel enrichment from 10.5 to 12.5%. At the optimum design of VSPINNOR terrace, burnup value obtained 17.63% HM (heavy metal), the pattern of distribution of neutron fairly evenly, the average power density of 363.56 watts/cc, and power peaking factor 1.21 with the value of the average excess reactivity <1%.
format Theses
author ARIANTO (NIM. 20211015); Pembimbing : Prof. Dr.Eng. Zaki Su'ud, FAJAR
spellingShingle ARIANTO (NIM. 20211015); Pembimbing : Prof. Dr.Eng. Zaki Su'ud, FAJAR
STUDY ON NEUTRONIC OF VERY SMALL PB - BI COOLED NO-ONSITE REFUELLING NUCLEAR POWER REACTOR (VSPINNOR)
author_facet ARIANTO (NIM. 20211015); Pembimbing : Prof. Dr.Eng. Zaki Su'ud, FAJAR
author_sort ARIANTO (NIM. 20211015); Pembimbing : Prof. Dr.Eng. Zaki Su'ud, FAJAR
title STUDY ON NEUTRONIC OF VERY SMALL PB - BI COOLED NO-ONSITE REFUELLING NUCLEAR POWER REACTOR (VSPINNOR)
title_short STUDY ON NEUTRONIC OF VERY SMALL PB - BI COOLED NO-ONSITE REFUELLING NUCLEAR POWER REACTOR (VSPINNOR)
title_full STUDY ON NEUTRONIC OF VERY SMALL PB - BI COOLED NO-ONSITE REFUELLING NUCLEAR POWER REACTOR (VSPINNOR)
title_fullStr STUDY ON NEUTRONIC OF VERY SMALL PB - BI COOLED NO-ONSITE REFUELLING NUCLEAR POWER REACTOR (VSPINNOR)
title_full_unstemmed STUDY ON NEUTRONIC OF VERY SMALL PB - BI COOLED NO-ONSITE REFUELLING NUCLEAR POWER REACTOR (VSPINNOR)
title_sort study on neutronic of very small pb - bi cooled no-onsite refuelling nuclear power reactor (vspinnor)
url https://digilib.itb.ac.id/gdl/view/20093
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