Study on The Ability of PCMSR to Produce Valuable Isotopes as By Produce of Energy Generation

PCMSR (Passive Compact Molten Salt Reactor) is a variant of MSR (Molten Salt Reactor) type reactors. The MSR is one type of the Advanced Nuclear Reactor types. PCMSR uses mixture of fluoride salt if liquid form in high temperature operation. The use of liquid salt fuel allows the application of on l...

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Main Author: Harto, Andang Widi
Format: Conference or Workshop Item
Language:English
Published: 2016
Subjects:
Online Access:https://repository.ugm.ac.id/275012/1/Procceding%202nd%20International%20Symposium%20on%20BNCT%20Study%20on%20the%20Ability%20of%20PCMSR%20to%20Produce%20Valuable%20Isotopes%20as%20By%20Product%20of%20Energy%20Generation.pdf
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author Harto, Andang Widi
author_facet Harto, Andang Widi
author_sort Harto, Andang Widi
collection UGM
description PCMSR (Passive Compact Molten Salt Reactor) is a variant of MSR (Molten Salt Reactor) type reactors. The MSR is one type of the Advanced Nuclear Reactor types. PCMSR uses mixture of fluoride salt if liquid form in high temperature operation. The use of liquid salt fuel allows the application of on line fuel processing system. The on line fuel processing system allow extraction of several valuable fission product isotopes such as Mo-99, Cs-137, Sr-89 etc. The capability to MSR to produce several valuable isotopes has been studied. This study based on a denaturated breeder MSR design with 920 MWth of thermal power and 500 MWe of electrical output power with the thermal efficiency of 55 %. The initial composition of fuel salt is 70 % mole of LiF, 24 % mole of 232ThF4, 6 % mole of UF4. The enrichment level of U is 20 % mole of U-235. The study is performed by numerical calculation to solve a set of differential equations of fission product ballance. This calculation calculates fission product generation due to fission reaction and precursor decay and fission product annihilation due to decay, neutron absorption and extraction. The calculation result shows that in quasy equilibrium condition, the reactor can produce several valuable isotopes in substantially sufficient quantities, those are Sr-89 (0.3 kCi/MWth/day, Sr-90 (1,91 Ci/MWth/day), Mo-99 (1.7 kCi/MWth/day), I-131 (0.42 kCi/MWth/day), I-132 (0.782 kCi/MWth/day), I-133 (1.12 kCi/MWth/day), Xe-133 (11.8 Ci/MWth/day), Cs-134 (39.3 mCi/MWth/day), Cs-137 (2.32 Ci/MWth/day) and La-140 (1.05 kCi/MWth/day). . Keywords PCMSR, fission product, valuable nuclides
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spelling oai:generic.eprints.org:2750122019-02-01T01:26:50Z https://repository.ugm.ac.id/275012/ Study on The Ability of PCMSR to Produce Valuable Isotopes as By Produce of Energy Generation Harto, Andang Widi Nuclear Engineering PCMSR (Passive Compact Molten Salt Reactor) is a variant of MSR (Molten Salt Reactor) type reactors. The MSR is one type of the Advanced Nuclear Reactor types. PCMSR uses mixture of fluoride salt if liquid form in high temperature operation. The use of liquid salt fuel allows the application of on line fuel processing system. The on line fuel processing system allow extraction of several valuable fission product isotopes such as Mo-99, Cs-137, Sr-89 etc. The capability to MSR to produce several valuable isotopes has been studied. This study based on a denaturated breeder MSR design with 920 MWth of thermal power and 500 MWe of electrical output power with the thermal efficiency of 55 %. The initial composition of fuel salt is 70 % mole of LiF, 24 % mole of 232ThF4, 6 % mole of UF4. The enrichment level of U is 20 % mole of U-235. The study is performed by numerical calculation to solve a set of differential equations of fission product ballance. This calculation calculates fission product generation due to fission reaction and precursor decay and fission product annihilation due to decay, neutron absorption and extraction. The calculation result shows that in quasy equilibrium condition, the reactor can produce several valuable isotopes in substantially sufficient quantities, those are Sr-89 (0.3 kCi/MWth/day, Sr-90 (1,91 Ci/MWth/day), Mo-99 (1.7 kCi/MWth/day), I-131 (0.42 kCi/MWth/day), I-132 (0.782 kCi/MWth/day), I-133 (1.12 kCi/MWth/day), Xe-133 (11.8 Ci/MWth/day), Cs-134 (39.3 mCi/MWth/day), Cs-137 (2.32 Ci/MWth/day) and La-140 (1.05 kCi/MWth/day). . Keywords PCMSR, fission product, valuable nuclides 2016-08-10 Conference or Workshop Item PeerReviewed application/pdf en https://repository.ugm.ac.id/275012/1/Procceding%202nd%20International%20Symposium%20on%20BNCT%20Study%20on%20the%20Ability%20of%20PCMSR%20to%20Produce%20Valuable%20Isotopes%20as%20By%20Product%20of%20Energy%20Generation.pdf Harto, Andang Widi (2016) Study on The Ability of PCMSR to Produce Valuable Isotopes as By Produce of Energy Generation. In: 2nd International Symposium on BNCT (Boron Neutron Capture Cancer Therapy) The Aplication of Nuclear Technology to Support National Sustainable Development, 10 - 11 Agustus 2016, Surakarta.
spellingShingle Nuclear Engineering
Harto, Andang Widi
Study on The Ability of PCMSR to Produce Valuable Isotopes as By Produce of Energy Generation
title Study on The Ability of PCMSR to Produce Valuable Isotopes as By Produce of Energy Generation
title_full Study on The Ability of PCMSR to Produce Valuable Isotopes as By Produce of Energy Generation
title_fullStr Study on The Ability of PCMSR to Produce Valuable Isotopes as By Produce of Energy Generation
title_full_unstemmed Study on The Ability of PCMSR to Produce Valuable Isotopes as By Produce of Energy Generation
title_short Study on The Ability of PCMSR to Produce Valuable Isotopes as By Produce of Energy Generation
title_sort study on the ability of pcmsr to produce valuable isotopes as by produce of energy generation
topic Nuclear Engineering
url https://repository.ugm.ac.id/275012/1/Procceding%202nd%20International%20Symposium%20on%20BNCT%20Study%20on%20the%20Ability%20of%20PCMSR%20to%20Produce%20Valuable%20Isotopes%20as%20By%20Product%20of%20Energy%20Generation.pdf
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