STUDY ON 233U AND PLUTONIUM UTILIZATION IN THORIUM MOLTEN SALT REACTOR WITH SMALL POWER 25-30 MWT

Molten Salt Reactor (MSR) are selected as one of the candidates of the generation IV reactor concept, since it has several advantages such as safety improvement, resource sustainability, waste burning, and proliferation resistance. Recently proposed a concept of Thorium Molten Salt Nuclear Energy Si...

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Main Author: RICHARDINA (NIM : 20210018); Pembimbing : Dr. Eng. Abdul Waris, VERY
Format: Theses
Language:Indonesia
Online Access:https://digilib.itb.ac.id/gdl/view/17498
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Institution: Institut Teknologi Bandung
Language: Indonesia
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spelling id-itb.:174982017-09-27T14:40:51ZSTUDY ON 233U AND PLUTONIUM UTILIZATION IN THORIUM MOLTEN SALT REACTOR WITH SMALL POWER 25-30 MWT RICHARDINA (NIM : 20210018); Pembimbing : Dr. Eng. Abdul Waris, VERY Indonesia Theses INSTITUT TEKNOLOGI BANDUNG https://digilib.itb.ac.id/gdl/view/17498 Molten Salt Reactor (MSR) are selected as one of the candidates of the generation IV reactor concept, since it has several advantages such as safety improvement, resource sustainability, waste burning, and proliferation resistance. Recently proposed a concept of Thorium Molten Salt Nuclear Energy Sinergetic(THORIMS-NES) with the first stage is the construction of miniFuji. miniFuji using 233U-Th as fuel with 5 years of refueling and 350 MWt output power. In this study we use 233U-Th and Plutonium-Thorium as fuel in miniFuji with various output power of 25-50 MWth and 20 years refueling. Plutonium composition consisting of Reactor Grade Plutonium and Weapon Grade <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> Plutonium. Composition of the 233U-Thorium used in this study were 1.20-1.60% 233U and 11.02-10.62% Thorium. Composition of Reactor Grade Plutonium-thorium used in this study are 8.26- 5.46% Th and 3.96-6.76% Pu. Fuel <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> composition of Weapon Grade Plutonium used in this study was 11.6-8.26% Thorium and 1.16-3.96% Plutonium. The results show that the required 233U concentrations for criticality are about 1.28% for 25 MWt, 1.34% for 30 MWt, 1.38% for 35 MWt, 1.44% for 40 MWt, 1.48% for 45 MWt and 1.54% for 50 MWt, respectively. For the fuel Reactor <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> Grade Plutonium the demans of Plutonium fractions for criticality are about 5.36% for 25-35 MWt and 5.56% for 40-50 MWt. For Weapon Grade Plutonium the need of Plutonium concentrations for criticality are about 2.96% for 25-30 MWt, 3.16% for 35-45% MWt and 3.36% for 50 MWt,respectively. 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 Molten Salt Reactor (MSR) are selected as one of the candidates of the generation IV reactor concept, since it has several advantages such as safety improvement, resource sustainability, waste burning, and proliferation resistance. Recently proposed a concept of Thorium Molten Salt Nuclear Energy Sinergetic(THORIMS-NES) with the first stage is the construction of miniFuji. miniFuji using 233U-Th as fuel with 5 years of refueling and 350 MWt output power. In this study we use 233U-Th and Plutonium-Thorium as fuel in miniFuji with various output power of 25-50 MWth and 20 years refueling. Plutonium composition consisting of Reactor Grade Plutonium and Weapon Grade <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> Plutonium. Composition of the 233U-Thorium used in this study were 1.20-1.60% 233U and 11.02-10.62% Thorium. Composition of Reactor Grade Plutonium-thorium used in this study are 8.26- 5.46% Th and 3.96-6.76% Pu. Fuel <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> composition of Weapon Grade Plutonium used in this study was 11.6-8.26% Thorium and 1.16-3.96% Plutonium. The results show that the required 233U concentrations for criticality are about 1.28% for 25 MWt, 1.34% for 30 MWt, 1.38% for 35 MWt, 1.44% for 40 MWt, 1.48% for 45 MWt and 1.54% for 50 MWt, respectively. For the fuel Reactor <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> <br /> Grade Plutonium the demans of Plutonium fractions for criticality are about 5.36% for 25-35 MWt and 5.56% for 40-50 MWt. For Weapon Grade Plutonium the need of Plutonium concentrations for criticality are about 2.96% for 25-30 MWt, 3.16% for 35-45% MWt and 3.36% for 50 MWt,respectively.
format Theses
author RICHARDINA (NIM : 20210018); Pembimbing : Dr. Eng. Abdul Waris, VERY
spellingShingle RICHARDINA (NIM : 20210018); Pembimbing : Dr. Eng. Abdul Waris, VERY
STUDY ON 233U AND PLUTONIUM UTILIZATION IN THORIUM MOLTEN SALT REACTOR WITH SMALL POWER 25-30 MWT
author_facet RICHARDINA (NIM : 20210018); Pembimbing : Dr. Eng. Abdul Waris, VERY
author_sort RICHARDINA (NIM : 20210018); Pembimbing : Dr. Eng. Abdul Waris, VERY
title STUDY ON 233U AND PLUTONIUM UTILIZATION IN THORIUM MOLTEN SALT REACTOR WITH SMALL POWER 25-30 MWT
title_short STUDY ON 233U AND PLUTONIUM UTILIZATION IN THORIUM MOLTEN SALT REACTOR WITH SMALL POWER 25-30 MWT
title_full STUDY ON 233U AND PLUTONIUM UTILIZATION IN THORIUM MOLTEN SALT REACTOR WITH SMALL POWER 25-30 MWT
title_fullStr STUDY ON 233U AND PLUTONIUM UTILIZATION IN THORIUM MOLTEN SALT REACTOR WITH SMALL POWER 25-30 MWT
title_full_unstemmed STUDY ON 233U AND PLUTONIUM UTILIZATION IN THORIUM MOLTEN SALT REACTOR WITH SMALL POWER 25-30 MWT
title_sort study on 233u and plutonium utilization in thorium molten salt reactor with small power 25-30 mwt
url https://digilib.itb.ac.id/gdl/view/17498
_version_ 1822018395952906240