ADVANCED SFR DESIGN CONCEPTS AND R&amp;D ACTIVITIES

Hahn, Dohee; Chang, Jonghwa; Kim, Young-In; Kim, Yeong-Il; Lee, Chan-Bock; Kim, Seong O; Lee, Jae-Han; Ha, Kwang Soon; Kim, Byung-Ho; Lee, Yongbum

doi:10.5516/net.2009.41.4.427

Cited by 19 publications

(8 citation statements)

References 6 publications

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“…The major losses are caused by friction between the duct and fluid in the annular gap of the ALIP, whereas minor losses occur at both ends of the flow gap, although reducer parts at the end of the flow gap can assist in reducing these losses. Both the major and minor hydraulic pressure losses can be predicted from Equations (7) and (8), respectively [17].…”

Section: Design Analysis Of An Alipmentioning

confidence: 99%

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Design and preliminary test of an annular linear induction electromagnetic pump for a sodium-cooled fast reactor thermal hydraulic experiment

Kwak

Kim

2017

Journal of Nuclear Science and Technology

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An annular linear induction electromagnetic pump (ALIP) with a flow rate of 2265 L/min and a developed pressure of 4 bar was designed and fabricated to test the performance of the components of a sodium-cooled fast reactor (SFR) in a sodium thermal hydraulic experimental loop. The design characteristic of the ALIP was calculated using the electrical equivalent circuit method typically used for analyzing linear induction machines. Preliminary tests, such as verification of the moving function using an annular Al pipe, were carried out. The linearity between the input voltage, current, and magnetic flux density was verified. The developed force demonstrated an increase proportional to the square of the input current, whereas the velocity was linearly proportional to the input current. The main design variables of the pump were calculated theoretically for the SFR thermal hydraulic experimental loop. The pump was optimized for the design variables including input frequency, and the characteristics of the optimized pump were compared with those of the pump at the commercially used frequency of 60 Hz.

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Section: Design Analysis Of An Alipmentioning

confidence: 99%

“…Owing to this advantage, the ALIP is employed for systems requiring large flow rates of liquid metal with high electrical conductivity [5]. Consequently, in sodium-cooled fast reactors (SFRs), where Na is used as the coolant, the ALIP was shown to exhibit good performance properties [6][7].…”

Section: Introductionmentioning

confidence: 99%

Design and preliminary test of an annular linear induction electromagnetic pump for a sodium-cooled fast reactor thermal hydraulic experiment

Kwak

Kim

2017

Journal of Nuclear Science and Technology

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“…Therefore, in a sodium‐cooled fast reactor (SFR), an electromagnetic pump can be effectively used to transport liquid sodium because of its simple structure with no rotating parts . This motivated us to develop large‐scale magnetohydrodynamic (MHD) transportation systems, particularly MHD circulators of the annular linear induction type; however, a large‐scale MHD circulator can cause MHD instability during its operation owing to a high flow rate in the flow channel . In the present study, critical developed pressure equations were derived from the theoretical model of an MHD circulator with a homogeneous velocity distribution.…”

Section: Introductionmentioning

confidence: 99%

“…3 This motivated us to develop large-scale magnetohydrodynamic (MHD) transportation systems, particularly MHD circulators of the annular linear induction type; however, a large-scale MHD circulator can cause MHD instability during its operation owing to a high flow rate in the flow channel. 4,5 In the present study, critical developed pressure equations were derived from the theoretical model of an MHD circulator with a homogeneous velocity distribution. The relations between MHD stability and design variables of the MHD circulator were analysed using dimensionless parameters to identify the stability boundary.…”

Section: Introductionmentioning

confidence: 99%

Stability boundary analysis of magnetohydrodynamic circulator for the intermediate heat transfer system of prototype gen IV sodium fast reactor

Kwak

Kim

2019

Int J Energy Res

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Summary One of the most important parts in the development of generation IV nuclear reactors is safety. In the research on generation IV sodium‐cooled fast reactors, magnetohydrodynamic (MHD) circulators have received attention for the stable transport of coolants. In this study, the stability of an MHD circulator was evaluated using a mathematical approach to obtain the critical value of the developed pressure. The critical developed pressure equation is a function of the flow rate and dimensionless parameters, which were derived from the theoretical model of the MHD circulator with a dimensionless scaled velocity, flow rate, and pressure. The stability conditions expressed using the critical value of the developed pressure and dimensionless parameters were investigated according to the changes in the main design variables of the MHD circulator. The relationships between the dimensionless parameters, stability, and main design variables constituting the stability boundary of the MHD circulator were analysed. The stability of the MHD circulator is considered safe when the stability criterion ε is lower than 1. The geometrical variables such as the duct thickness or width of the flow gap and electrical variables such as the frequency were the main parameters affecting the flow stability in the MHD circulator.

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“…Along with safety, these environmental problems are the major factors influencing the sustainability of nuclear power. As one of the potential approaches to manage nuclear wastes, Korea is exploring the closed fuel cycle regarding deep geological disposal, pyroprocessing, and sodium-cooled fast reactors (SFRs) to demonstrate its technical, economical, and socio-political feasibility [1,2].…”

Section: Introductionmentioning

confidence: 99%

Dynamic assessments on high-level waste and low- and intermediate-level waste generation from open and closed nuclear fuel cycles in Republic of Korea

Choi¹,

Ko²

2014

Journal of Nuclear Science and Technology

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We estimated the generation of low-and intermediate-level waste (LILW) and high-level waste (HLW) from open and closed nuclear fuel cycles. The closed fuel cycle reflects the development and deployment of fast reactors and pyroprocessing from 2013 to 2100, while the open fuel cycle only considers pressurized water reactors. The closed fuel cycle hardly affects short-term spent fuel management but can save nearly 60% space of interim storage compared with the open fuel cycle. Compared with the open fuel cycle, the accumulated volume of HLW can be significantly reduced in the closed fuel cycle up to over 95% in 2100. For this volume reduction, high heat generating fission products should be separated from transuranic waste in pyroprocessing and stored in decay storages for a few hundred years. Mining and milling waste in the closed fuel cycle decreases by about 31%. In contrast, the closed fuel cycle generates 3.0%-4.5% more LILW than the open fuel cycle because fast reactors and pyroprocessing produce more LILW and conversion, enrichment, and fabrication produce less LILW. In the closed fuel cycle, operation and decommissioning wastes from reactor and pyroprocessing, respectively, contribute to 74% and 8% of LILW excluding mining and milling waste.

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ADVANCED SFR DESIGN CONCEPTS AND R&D ACTIVITIES

Cited by 19 publications

References 6 publications

Design and preliminary test of an annular linear induction electromagnetic pump for a sodium-cooled fast reactor thermal hydraulic experiment

Design and preliminary test of an annular linear induction electromagnetic pump for a sodium-cooled fast reactor thermal hydraulic experiment

Stability boundary analysis of magnetohydrodynamic circulator for the intermediate heat transfer system of prototype gen IV sodium fast reactor

Dynamic assessments on high-level waste and low- and intermediate-level waste generation from open and closed nuclear fuel cycles in Republic of Korea

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