Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea

Yoo, Juhyun; Chang, Jonghwa; Lim, Jinhyuk; Cheon, Jin-Sik; Lee, Tae‐Ho; Kim, Sung Kyun; Lee, Kwi Lim; Joo, Hyung-Kook

doi:10.1016/j.net.2016.08.004

Cited by 66 publications

(11 citation statements)

References 4 publications

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“…Steam is produced at inlet and outlet temperatures of around 230 and 503 °C, respectively, with inlet and outlet pressures of 18 and 16.7 MPa, respectively. Sodium flows at inlet and outlet temperatures of around 528 and 322 °C, respectively, with a pressure of 0.5 MPa [25]. Here, a new design for the printed circuit steam generator is proposed.…”

Section: Approach and Pche Designmentioning

confidence: 99%

Mechanical Integrity Analysis of a Printed Circuit Heat Exchanger with Channel Misalignment

Simanjuntak

Lee

2020

Applied Sciences

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Printed circuit heat exchangers (PCHEs), which are used for thermal heat storage and power generation, are often subject to severe pressure and temperature differences between primary and secondary channels, which causes mechanical integrity problems. PCHE operation may result in discontinuity, such as channel misalignment, due to non-uniform thermal fields in the diffusion bonding process. The present paper analyzes the mechanical integrity, including the utilization factors of stress and deformation under various channel misalignment conditions. The pressure difference of the target PCHE is 19.5 MPa due to the high pressure (19.7 MPa) of the steam channel in the Rankine cycle and the low pressure (0.5 MPa) of molten salt or liquid metal in the primary channel. Additionally, the temperature difference between channels is around 25 °C, however the average temperature is around 500 °C. The PCHE has a relatively large primary channel measuring approximately 3 x 3 mm, and a steam channel measuring 2 x 1.5 mm. The finite element method (FEM) is applied to determine the stress by changing the misalignment to below 30% of the primary channel width. It was found that the current PCHE is operable up to 700 °C in terms of the ASME code under these design conditions. Additionally, the change of utilization factor due to the misalignment increases, but is still under the ASME acceptance criteria of 700 °C; however, it violates the criteria at 725 °C, which is the allowable temperature condition. Therefore, the mechanical integrity of the PCHE with low-pressure molten salt or liquid metal and a high-pressure steam channel is acceptable in terms of utilization factor.

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Section: Approach and Pche Designmentioning

confidence: 99%

Mechanical Integrity Analysis of a Printed Circuit Heat Exchanger with Channel Misalignment

Simanjuntak

Lee

2020

Applied Sciences

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“…The main vital factor which differentiates the LOHSWS and LOFWS feedback in oxide and among two fuels the difference in metal fuel at stored Doppler reactivity. The settled Doppler reactivity reveals back as an essential input as the power is decreased, attending to remove the drawback because of the increase in coolant temperature [16,17]. Thus, the force is decreased quickly.…”

Section: Safety Passive Inherentmentioning

confidence: 99%

Advancement of Integral Fast Reactor

Ali

Raza

Muhammad

et al. 2020

Journal of Applied and Emerging Sciences

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In this paper, the advancement of the integral fast reactor (IFR) is studied. We proposed the safety passive inherent approach which keeps the IFR operations safe from the maintenance cost. Additionally, it is observed that when failure appears in the reactor then safety passive inherent works efficiently and it turns off the reactor to preserve the safety. Therefore, it is necessary to use the inherent properties of the metallic fuel such as liquid metal, and it should be cooled in a way to substantial developments in the total appearances of the reactor system. Moreover, the key advantages of the IFR concept are narrated briefly with its mechanic position and the future development and research directions.

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“…The Korea Atomic Energy Research Institute (KAERI) created a reactor design with the final goal of constructing a Prototype Gen-IV Sodium-cooled Fast Reactor (PGSFR) [3]. The main objective of the PGSFR was to verify transuranic (TRU) metal fuel performance, reactor operation, and transmutation ability of high-level wastes.…”

Section: Introductionmentioning

confidence: 99%

Experimental Validation of Flow Uniformity Improvement by a Perforated Plate in the Heat Exchanger of SFR Steam Generator

Nguyen

Jung

et al. 2021

Energies

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The steam generator in a nuclear power plant is a type of heat exchanger in which heat transfer occurs from the hot fluid in multiple channels to the cold fluid. Therefore, a uniform flow over multiple channels is necessary to improve heat exchanger efficiency. The study aims at experimentally investigating the improvement of flow uniformity by the perforated plate in the heat exchanger used for a sodium-cooled fast reactor stream generator. A 1/4-scale experimental model for one heat exchanger unit with 33 × 66 channels was manufactured. The working fluid was water. A perforated plate was systematically designed using numerical simulations to improve the flow uniformity over the 33 × 66 channels. As a result, the flow uniformity greatly improved at a slight cost of pressure drop. To validate the numerical results, planar particle image velocimetry measurements were performed on the selected planes in the inlet and outlet headers. The experimental velocity profiles near the exits of the channels were compared with numerical simulation data. The experimental profiles agreed with the numerical data well. Both the numerical simulation and the experimental results showed a slight increase in pressure drop, despite significant improvement in the flow uniformity.

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Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea

Cited by 66 publications

References 4 publications

Mechanical Integrity Analysis of a Printed Circuit Heat Exchanger with Channel Misalignment

Mechanical Integrity Analysis of a Printed Circuit Heat Exchanger with Channel Misalignment

Advancement of Integral Fast Reactor

Experimental Validation of Flow Uniformity Improvement by a Perforated Plate in the Heat Exchanger of SFR Steam Generator

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