Sensitivity study of parameters important to Molten Salt Reactor Safety

Creasman, Sarah Elizabeth; Pathirana, Visura; Chvála, O.

doi:10.1016/j.net.2023.02.002

Cited by 3 publications

(2 citation statements)

References 9 publications

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“…This design allows for more efficient heat transfer and better temperature control than conventional nuclear reactors. MSR is considered one of the Generation IV reactor types designed to enhance efficiency and safety and reduce environmental impact and nuclear proliferation risk [7,8]. There are five other types of Generation IV nuclear reactors,…”

Section: Introductionmentioning

confidence: 99%

Effect of Different Temperature and Nuclear Data Libraries in Criticality Calculations of 300 MWt Molten Salt Reactor

Variastuti,

Irwanto

2024

J. Phys.: Conf. Ser.

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The Molten Salt Reactor (MSR) is a type of reactor in which coolant and fuel are blended with liquid salts. Liquid fuel enhances heat transfer and temperature control, establishing the MSR as one of the Generation IV reactor types. This study aims to analyze the impact of temperature variations on MSR reactor criticality and evaluate the effect of different nuclear data libraries, namely JENDL 3.2, JENDL 3.3, and JENDL 4.0, in neutron analysis. The observed temperature variations are 600 K, 700 K, 833 K, 903 K, and 1000 K. The analysis spans low to operational temperatures to comprehend reactor performance under differing thermal conditions. The study is conducted on a 300 MWTh MSR design, utilizing SRAC2006 with PIJ and CITATION modules for calculations. The results reveal the impact of temperature variations and nuclear data library disparities on reactor criticality. The outcomes demonstrate that higher temperatures correspond to lower values of the effective multiplication factor. At lower temperatures, neutrons experience greater moderation compared to higher temperatures. As a result, a higher number of thermal neutrons influences an increased probability of fission reactions within the reactor. Different nuclear data libraries also yield varied criticality values due to differing cross-sectional areas and quantities of data within each JENDL library. JENDL 4.0 generates the highest criticality value, attributed to elevated cross-sectional regions of each respective nuclear data entry and a greater quantity of nuclear data entries than JENDL 3.2 and JENDL 3.3.

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Section: Introductionmentioning

confidence: 99%

Effect of Different Temperature and Nuclear Data Libraries in Criticality Calculations of 300 MWt Molten Salt Reactor

Variastuti,

Irwanto

2024

J. Phys.: Conf. Ser.

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“…Online refueling and chemical processing are also possible within MSR operations. However, there are some challenges, such as liquid fuels which affect the physical properties of other solid components because they interaction, and corrosion problems which also need to be considered [13,14]. This research was conducted with a focus on increasing the safety factor in the MSR design from the aspect of equal distribution of power distribution on the core so as not to allow system failure on the core due to high power at certain points.…”

Section: Introductionmentioning

confidence: 99%

Optimization of Core Regions and Fuel Fractions for Better Power Peaking Factor of 150, 450 and 1,000 MWth Molten Salt Reactor

Variastuti,

Irwanto,

Subkhi

et al. 2023

Trends Sci

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The power peaking factor (PPF) is an important parameter that needs to be considered to maintain the reactor's stability, safety and efficiency. The present study discusses the power density distribution in the reactor core by calculating the PPF to increase the reactor safety margin and minimize the possibility of a high power density at a certain point causing core failure in the Molten Salt Reactor (MSR), which is one of the Generation-IV reactors with fuel and coolant dissolved in molten salt. Important parameters discussed in the present study are the distribution of the reactor core region and the fuel composition in each region during the reactor operation time of 2,000 days. Analysis was performed for 3 different thermal power: 150, 450 and 1,000 MWth as a representative to determine the behavior of PPF at small to large power by taking the reference design of the FUJI U3 reactor developed by ITMSF (International Thorium Molten-Salt Forum) Japan. FliBe (Lithium and Beryllium Fluoride) is used as the coolant, and the fuel mixture is 233UF4-ThF4. The calculation was conducted using SRAC2006 with PIJ and CITATION modules that solve the neutron diffusion equation providing power distribution values and effective multiplication factors. As a result, the MSR with 4 core regions produces a more balanced power distribution, a better PPF value, and a good effective multiplication factor for 2,000 days of operation time compared to the reference design. HIGHLIGHTS The research emphasizes the analysis of thermal power levels of 150, 450, and 1000 MWth to understand the Power Peaking Factor (PPF) behavior at different power levels An even power distribution is accomplished by optimizing the number of core regions with different fuel fractions After optimization, the decrease in Power Peaking Factor (PPF) values indicates an improvement in maintaining reactor stability, safety, and efficiency GRAPHICAL ABSTRACT

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Molten salt reactor system dynamics in simulink and modelica, a code to code comparison

Pathirana

Creasman

Chvála

et al. 2023

Nuclear Engineering and Design

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Sensitivity study of parameters important to Molten Salt Reactor Safety

Cited by 3 publications

References 9 publications

Effect of Different Temperature and Nuclear Data Libraries in Criticality Calculations of 300 MWt Molten Salt Reactor

Effect of Different Temperature and Nuclear Data Libraries in Criticality Calculations of 300 MWt Molten Salt Reactor

Optimization of Core Regions and Fuel Fractions for Better Power Peaking Factor of 150, 450 and 1,000 MWth Molten Salt Reactor

Molten salt reactor system dynamics in simulink and modelica, a code to code comparison

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