• Title/Summary/Keyword: SMART reactor

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Steady-State Performance Analysis of Pressurizer and Helical Steam Generator for SMART

  • Seo, Jae-Kwang;Kang, Hyung-Seok;Kim, Hwan-Yeol;Cho, Bong-Hyun;Lee, Doo-Jeong
    • Proceedings of the Korean Nuclear Society Conference
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    • 1997.05a
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    • pp.310-315
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    • 1997
  • System-Integrated Modular Advanced Reactor (SMART), where major primary components such as modular helical steam generator and self regulating pressurizer are integrated into reactor vessel, is currently under development. The pressurizer is designed to control the primary pressure mainly with partial pressure of nitrogen gas and to maintain the fluid temperature as low as possible for the purpose of minimizing steam contribution. The steam generator (SG) is designed to produce super-heated steam inside tube at power operation. Because the in-vessel pressurizer and in-vessel SG are classified as the characteristic components of SMART, it is important to perform a steady state calculation of these components in order to evaluate the adoption of these components. A steady state analysis of the in-vessel pressurizer and in-vessel SG has been performed under normal power operation and the results show an acceptable performance of the components.

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A Study on the Design of the Motor Driving a Control-Rod for SMART (원자로 제어봉 구동용 전동기의 설계에 관한 연구)

  • Jeong, Y.H.;Kang, D.H.;Kim, J.M.;Im, T.Y.
    • Proceedings of the KIEE Conference
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    • 2000.07b
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    • pp.714-716
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    • 2000
  • In the System-integrated modular advanced reactor(SMART), the motor for Control element drive mechanism(CEDM) requires high density power and simple drive mechanism to reduce volume because of restriction by install-space and must satisfy the reactor operating circumstances with high pressure and temperature. In this paper, we perform the basic design of the two kinds (Variable reluctance type and Hibrid-reluctance type) of the transverse flux motor to develop the prototype motor for the control element drive mechanism of SMART. Analyzed these motors by the FEM in the 2-dimension, we show the characteristics for each of the analysis model.

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Contribution of thermal-hydraulic validation tests to the standard design approval of SMART

  • Park, Hyun-Sik;Kwon, Tae-Soon;Moon, Sang-Ki;Cho, Seok;Euh, Dong-Jin;Yi, Sung-Jae
    • Nuclear Engineering and Technology
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    • v.49 no.7
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    • pp.1537-1546
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    • 2017
  • Many thermal-hydraulic tests have been conducted at the Korea Atomic Energy Research Institute for verification of the SMART (System-integrated Modular Advanced ReacTor) design, the standard design approval of which was issued by the Korean regulatory body. In this paper, the contributions of these tests to the standard design approval of SMART are discussed. First, an integral effect test facility named VISTA-ITL (Experimental Verification by Integral Simulation of Transients and Accidents-Integral Test Loop) has been utilized to assess the TASS/SMR-S (Transient and Set-point Simulation/Small and Medium) safety analysis code and confirm its conservatism, to support standard design approval, and to construct a database for the SMART design optimization. In addition, many separate effect tests have been performed. The reactor internal flow test has been conducted using the SCOP (SMART COre flow distribution and Pressure drop test) facility to evaluate the reactor internal flow and pressure distributions. An ECC (Emergency Core Coolant) performance test has been carried out using the SWAT (SMART ECC Water Asymmetric Two-phase choking test) facility to evaluate the safety injection performance and to validate the thermal-hydraulic model used in the safety analysis code. The Freon CHF (Critical Heat Flux) test has been performed using the FTHEL (Freon Thermal Hydraulic Experimental Loop) facility to construct a database from the $5{\times}5$ rod bundle Freon CHF tests and to evaluate the DNBR (Departure from Nucleate Boiling Ratio) model in the safety analysis and core design codes. These test results were used for standard design approval of SMART to verify its design bases, design tools, and analysis methodology.

Investigation of condensation with non-condensable gas in natural circulation loop for passive safety system

  • Jin-Hwa Yang;Tae-Hwan Ahn;Hwang Bae;Hyun-Sik Park
    • Nuclear Engineering and Technology
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    • v.55 no.3
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    • pp.1125-1139
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    • 2023
  • The system-integrated modular advanced reactor 100 (SMART100), an integral-type pressurized water small modular reactor, is based on a novel design concept for containment cooling and radioactive material reduction; it is known as the containment pressure and radioactivity suppression system (CPRSS). There is a passive cooling system using a condensation with non-condensable gas in the SMART CPRSS. When a design basis accident such as a small break loss of coolant accident (SBLOCA) occurs, the pressurized low containment area (LCA) of the SMART CPRSS leads to steam condensation in an incontainment refuelling water storage tank (IRWST). Additionally, the steam and non-condensable gas mixture passes through the CPRSS heat exchanger (CHX) submerged in the emergency cooldown tank (ECT) that can partially remove the residual heat. When the steam and non-condensable gas mixture passes through the CHX, the non-condensable gas can interrupt the condensation heat transfer in the CHX and it degrades CHX performance. In this study, condensation heat transfer experiments of steam and non-condensable gas mixture in the natural circulation loop were conducted. The pressure, temperature, and effects of the non-condensable gas were investigated according to the constant inlet steam flow rate with non-condensable gas injections in the loop.

PARAMETRIC STUDIES ON THERMAL HYDRAULIC CHARACTERISTICS FOR TRANSIENT OPERATIONS OF AN INTEGRAL TYPE REACTOR

  • Choi, Ki-Yong;Park, Hyun-Sik;Cho, Seok;Yi, Sung-Jae;Park, Choon-Kyung;Song, Chul-Hwa;Chung, Moon-Ki
    • Nuclear Engineering and Technology
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    • v.38 no.2
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    • pp.185-194
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    • 2006
  • Transient operations for an integral type reactor, SMART-P, have been experimentally investigated using a thermal-hydraulic integral test facility, VISTA (Experimental Verification by Integral Simulation of Transients and Accidents), in order to verify the system design and performance of the SMART-P, a pilot plant of SMART. The VISTA facility was subjected to various accident conditions such as feedwater increase and decrease, loss of coolant flow, and control rod withdrawal accidents in order to elucidate the thermal-hydraulic responses following such accidents and finally to verify the system design of the SMARTP. Full functional control logics have been implemented in the VISTA facility in order to control the required control action for an accident simulation. As one of the sensitivity tests to verify the PRHRS performance, the effects of the initial water level in the compensation tank are experimentally investigated. When the initial water level is 16%, the water is quickly drained and nitrogen gas is then introduced into the PRHR system, resulting in deterioration of the PRHRS performance. It is thus found that nitrogen ingression should be prevented to ensure stable PRHRS operation.

Dynamic equivalent model of a SMART control rod drive mechanism for a seismic analysis

  • Ahn, Kwanghyun;Lee, Jae-Seon
    • Nuclear Engineering and Technology
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    • v.52 no.8
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    • pp.1834-1846
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    • 2020
  • The SMART (System-integrated Modular Advanced ReacTor) is an integral-type small modular reactor developed by KAERI (Korea Atomic Energy Research Institute). This paper discusses the development of a dynamic equivalent model of the SMART control rod drive mechanism that can be efficiently utilized for complicated analysis during the design of the SMART. A semi-empirical approach is used to develop the equivalent model; that is, the equivalent model is defined analytically and verified empirically. Two types of tests, dynamic characteristics tests and seismic loading tests, are conducted for the development and verification of the dynamic equivalent model, respectively. Acceleration response spectra from the seismic analysis based on the developed equivalent model show good agreement with those from the seismic loading tests.

Thermal Analysis of a Canned Induction Motor for Main Coolant Pump in System-Integrated Modular Advanced Reactor

  • Huh, Hyung;Kim, Jong-In;Kim, Kern-Jung
    • KIEE International Transaction on Electrical Machinery and Energy Conversion Systems
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    • v.3B no.1
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    • pp.32-36
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    • 2003
  • The three-phase canned induction motor, which consists of a stator and rotor with a seal can, is used for the main coolant pump (MCP) of the System-integrated Modular Advanced Reactor (SMART). The thermal characteristics of the can must be estimated exactly, since the eddy current loss of the can is a dominant parameter in design. Besides the insulation of the motor winding is compared of Teflon, glass fiber, and air, so it is not an easy task to analyze. A FEM thermal analysis was per-formed by using the thermal properties of complex insulation which were obtained by comparing the results of finite element thermal analysis and those of the experiment. As a result, it is shown that the characteristics of prototype canned induction motor have a good agreement with the results of FEM.

Thermal Analysis of Electromagnet for SMART Control Element Drive Mechanism (SMART용 볼너트-스크류형 제어봉구동장치에 장착되는 전자석의 열해석)

  • Huh, Hyung;Kim, Ji-Ho;Kim, Jong-In
    • Proceedings of the KIEE Conference
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    • 1999.11b
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    • pp.98-100
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    • 1999
  • A thermal analysis was performed for the electromagnet which is installed in the control element drive mechanism(CEDM) of the integral reactor SMART. A model for the thermal analysis of the electromagnet was developed and theoretical bases for the model were established. It is important that the temperature of the electromagnet windings be maintained within the allowable limit of the insulation, since the electromagnet of CEDM is always supplied with current during the reactor operation. So the thermal analysis of the winding insulation which is composed of polyimide and air were performed by finite element method. The thermal properties obtained here will be used as input for the optimization analysis of the electromagnet.

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DESIGN SCOPE AND LEVEL FOR STANDARD DESIGN CERTIFICATION UNDER A TWO STEP LICENSING PROCESS

  • Suh, Nam-Duk;Huh, Chang-Wook
    • Nuclear Engineering and Technology
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    • v.44 no.6
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    • pp.689-696
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    • 2012
  • A small integral reactor SMART (System Integrated Modular Advanced ReacTor), being developed in Korea since late 1990s and targeted to obtaining a standard design approval by the end of 2011, is introduced. The design scope and level for design certification (DC) is well described in the U.S. NRC SECY documents published the early 1990s. However, the documents are valid for a one-step licensing process called a combined operating license (COL) by the U.S. NRC, while Korea still uses a two-step licensing process. Thus, referencing the concept of the SECY documents, we have established the design scope and level for the SMART DC using the contexts of the standard review plan (SRP). Some examples of the results and issues raised during our review are briefly presented in this paper. The same methodology will be applied to other types of reactor under development in Korea, such as future VHTR reactors.