Sustainable criticality analysis of PCMSR fuel using thorium as sustainable fuel and low enriched uranium as starting fuel

Harto, Andang Widi

doi:10.1504/ijnest.2015.074098

Cited by 12 publications

(8 citation statements)

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“…The thorium is converted to fissile U-233 which undergoes fission reaction and produces the reactor power. The PCMSR use graphite as moderator and LiF-NaF-KF as intermediate coolant [12]. The schematic diagram of PCMSR is shown in Fig.…”

Section: Pcmsr (Passive Compact Molten Saltmentioning

confidence: 99%

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Mass and Energy Balance Analysis of Methanol Production Using Atmospheric CO2 Capture with Energy Source from PCMSR

Harto

Soelanda

2018

E3S Web Conf.

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The rising of atmospheric CO2 concentration is the major source to global warming system. Many methods have been proposed to mitigate global warming, such as carbon penalty, carbon trading, CO2 sequestration, etc. However these proposed methods are usually uneconomical, i.e., these methods do not produce economic valuable substances. This paper will propose a method to absorb atmospheric CO2 to produce economic valuable substances such as methanol, dimethyl ether, ethylene, several hydrocarbon substances and derivatives and several graphite substances. This paper is focused on methanol production using atmospheric CO2 capture. The overall process is endothermic. Thus a sufficient energy source is needed. To avoid more CO2 emission, the energy source must not use conventional fuels. To assure the continuity of energy deliberation, nuclear energy will be used as the energy source of the process. In this paper, the Passive Compact Molten Salt Reactor (PCMSR) will be used as the energy source. The 460 MWth PCMSR is coupled with atmospheric CO2 capture, desalination, hydrogen production and methanol production facilities. The capturing CO2 capacity is 7.2 ton/h of atmospheric CO2. The valuable outputs of this system are 3.34 ton/h of H2, 34.56 ton/h of O2, 5.24 ton/h of methanol and 86.74 MWe of excess electricity.

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Section: Pcmsr (Passive Compact Molten Saltmentioning

confidence: 99%

“…Schematic diagram of energy balance of hydrogen production using High-Temperature Steam Electrolysis using energy source from PCMSR The schematic diagram of PCMSR[12] The g Δ component must be supplied as electrical energy. Thus the electrical power needed to supply the g…”

mentioning

confidence: 99%

Mass and Energy Balance Analysis of Methanol Production Using Atmospheric CO2 Capture with Energy Source from PCMSR

Harto

Soelanda

2018

E3S Web Conf.

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“…As a liquid-fuelled reactor, MSR offers many advantages compared to conventional light water reactors. Among them are [1][2][3][4][5],  Atmospheric operational pressure due to high boiling point of salt, eliminating the need of pressure vessel.  Operability in high temperature (700 °C and higher).…”

Section: Introductionmentioning

confidence: 99%

“…MSR is offered in various designs; moderated [4,[6][7][8][9][10] or unmoderated [11][12][13][14][15][16], fluoride or chloride, thorium or uranium. Most MSR researches and designs favor thermal MSR, leaving only a handful of designs of fast MSRs, such as French MSFR [11], TerraPower's MCFR [17], and Elysium Industries' MCSFR [18].…”

Section: Introductionmentioning

confidence: 99%

Neutronic Analysis of LEU-started Molten Chloride Fast Reactor without Fuel Reprocessing

Dwijayanto

Harto

2021

CERiMRE

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One of the rarely explored molten salt reactor (MSR) designs is the molten chloride fast reactor (MCFR). This MSR design employs chloride salt instead of fluoride and operated in a fast spectrum. MCFR brings all the advantages of an MSR including breeding whilst being able to burn plutonium and minor actinides efficiently. Since not many countries have access to civilian plutonium, MCFR can also be started using low-enriched uranium (LEU). This study is an initial neutronic analysis of an MCFR using LEU as its startup fuel. Parameters analyzed are conversion ratio (CR) and its neutronic safety, namely effective delayed neutron fraction (βeff), temperature coefficient of reactivity (TCR), and void coefficient of reactivity (VCR). The core is divided into Core Zone and Blanket Zone. The fuel composition of NaCl-UCl3 with a molar fraction ratio of 60:40 and 50:50 is used in Core Zone and Blanket Zone, respectively. The neutronic calculation is performed using MCNP6 code with ENDF/B-VII library. For reference geometry, CR is valued at 0.9298, βeff at 0.00731, TCR at -19.8 pcm/°C, and average VCR at -154.31 pcm/void%. Thereby, the MCFR fulfills inherent safety criteria. Although its value is remarkably high, CR can be further optimized by modifying the separator and reflector material.

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“…This feature is ideal to utilise thorium, which technically capable of breeding in thermal spectrum. Thus, many MSR concepts are designed to use thorium in its fuel [4][5][6][7]. MSR operating in pure thorium fuel cycle requires thorium as its fertile fuel and 233 U as its fissile fuel [4,6].…”

Section: Introduction *mentioning

confidence: 99%

Investigation on Inherent Safety of One Fluid-Molten Salt Reactor (Of-Msr) With Various Starting Fuel

Dwijayanto

Hermawan

2020

Tri Dasa Mega

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Molten salt reactor (MSR) is often associated with thorium fuel cycle, thanks to its excellent neutron economy and online reprocessing capability. However, since 233U, the fissile used in pure thorium fuel cycle, is not commercially available, the MSR must be started with other fissile nuclides. Different fissile yields different inherent safety characteristics, and thus must be assessed accordingly. This paper investigates the inherent safety aspects of one fluid MSR (OF-MSR) using various fissile fuel, namely low-enriched uranium (LEU), reactor grade plutonium (RGPu), and reactor grade plutonium + minor actinides (PuMA). The calculation was performed using MCNPX2.6.0 programme with ENDF/B-VII library. Parameters assessed are temperature coefficient of reactivity (TCR) and void coefficient of reactivity (VCR). The result shows that TCR for LEU, RGPu, and PuMA are -3.13 pcm, -2.02 pcm and -1.79 pcm, respectively. Meanwhile, the VCR is negative only for LEU, whilst RGPu and PuMA suffer from positive void reactivity. Therefore, for the OF-MSR design used in this study, LEU is the only safe option as OF-MSR starting fuel.Keywords: MSR, Temperature coefficient of reactivity, Void coefficient of reactivity, Low enriched uranium, Reactor grade plutonium, Minor actinides

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Sustainable criticality analysis of PCMSR fuel using thorium as sustainable fuel and low enriched uranium as starting fuel

Cited by 12 publications

References 0 publications

Mass and Energy Balance Analysis of Methanol Production Using Atmospheric CO2 Capture with Energy Source from PCMSR

Mass and Energy Balance Analysis of Methanol Production Using Atmospheric CO2 Capture with Energy Source from PCMSR

Neutronic Analysis of LEU-started Molten Chloride Fast Reactor without Fuel Reprocessing

Investigation on Inherent Safety of One Fluid-Molten Salt Reactor (Of-Msr) With Various Starting Fuel

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