• Title/Summary/Keyword: Gen-IV

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Impingement wastage experiment with SUS 316 in a printed circuit steam generator

  • Siwon Seo;Bowon Hwang;Sangji Kim;Jaeyoung Lee
    • Nuclear Engineering and Technology
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    • v.56 no.1
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    • pp.257-264
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    • 2024
  • The sodium cooled fast reactor (SFR) is one of the Gen-IV reactors with the most operating experience accumulated. Although the technology level is the most mature among the Gen-IV reactors, there is still a safety problem that has not been solved, which is the sodium-water reaction. Since sodium and water are separated only by a heat transfer tube with a thickness of only a few mm, there is inherently a risk of a sodium-water reaction (SWR) accident in the SFR. In this study, it is attempted to quantitatively evaluate the resistance of SWR accidents by replacing the shell and tube steam generator with printed circuit steam generator (PCSG) as a method to mitigate the SWR accident. To do this, a CATS-S (Compact Accident Tolerance Steam Generator-SWR) facility was designed and built. And for the quantitative evaluation of accident resistance, a methodology for measuring the impingement wastage rate was established. As a result of this research, the impingement wastage rate caused by SWR generated in a PCSG was measured first time. It was confirmed that the impingement wastage phenomenon was suppressed in the PCSG, and the accident resistance was higher than that of the SWR through comparison with the experimental results performed in the existing shell and tube steam generator. In conclusion, a PCSG is more resistant to impingement wastage as a result of the SWR accident than existing shell and tube steam generators, and it is estimated that a PCSG can mitigate SWR accidents, an inherent problem of SFR.

Isolation and Characterization of a Novel Triolein Selective Lipase from Soil Environmental Genes

  • Lim, Hee Kyung;Han, Ye-Jin;Hahm, Moon-Sun;Park, Soo Youl;Hwang, In Taek
    • Microbiology and Biotechnology Letters
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    • v.48 no.4
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    • pp.480-490
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    • 2020
  • A novel lipase gene, Lip-1420, was isolated from a metagenomic library constructed from reed marsh from Mt. Jumbong in Korea, comprising 112,500 members of recombinant plasmids. The DNA sequence of Lip-1420-subclone (5,513 bp) was found to contain at least 11 ORFs according to the GenBank database. The ORF-3 gene was inserted into the pET21a plasmid containing the C-terminal 6-His tag and transformed into E. coli BL21(DE3) to express the recombinant lipase protein. Lip-1420 was purified using a fast protein liquid chromatography system. The gene was registered in GenBank (MH628529). The values of Km and Vmax were determined as 0.268 mM and 1.821 units, respectively, at 40℃ and pH 8.0, using p-nitrophenyl palmitate as the substrate. This lipase belongs to family IV taxonomically because it has conserved HGGG and GDSAG motifs in the constitutive amino acid sequence. According to the predicted structural model, the binding sites are represented by residues H78, G81, D150, S151, A152, V181, and D236. Finally, Lip-1420 showed triolein selectivity for methanolysis between triolein (18:1) and tristearin (18:0) substrates. Further study of the selective mechanism and structure-function relationship of this new lipase could be useful for more practical applications.

Genetic Diversity of Two Isolates in Strawberry mild yellow edge virus from Korea (국내에서 분리한 딸기누른오갈바이러스의 유전적 다양성)

  • Kwon, Sun-Jung;Cho, In-Sook;Yoon, Ju-Yeon;Choi, Gug-Seoun
    • Research in Plant Disease
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    • v.24 no.4
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    • pp.285-291
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    • 2018
  • Two isolates of Strawberry mild yellow edge virus were newly isolated in strawberry (Fragaria x ananassa) cultivar Selhyang and Kamhong from Korea. The complete nucleotide sequence of the coat protein (CP) of two Korean isolates were determined and analyzed. Sequence identity of nucleotide and amino acid between SH and KH isolates was 90.4% and 95.5%, respectively. The comparison of three Korean isolates including previously reported KNS1 with 45 SMYEV sequences from other countries deposited in GenBank database revealed an identity ranging from 81.2% to 100%. The phylogenetic analysis of CP of all SMYEV isolates showed the five subgroups (I-V), with Korean isolates being divided into two different subgroups. The isolates KH and KNS1 were included in subgroup I, whereas SH was included in subgroup IV which is new phylogenetic subgroup. Genetic diversity analysis indicated that new subgroup had greater variability and nucleotide diversity between subgroups resulted in values ranging from 0.0863 to 0.18004. This report represents the first molecular characterization of SMYEV isolates from Korea.

Drop Performance Test of Control Rod Assembly for Prototype Gen-IV Sodium-cooled Fast Reactor (PGSFR 제어봉집합체 낙하성능시험)

  • Lee, Young Kyu;Kim, Hoe Woong;Lee, Jae Han;Koo, Gyeong Hoi;Kim, Jong Bum;Kim, Sung Kyun
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.12 no.1
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    • pp.134-140
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    • 2016
  • The Control Rod Assembly (CRA) controls the reactor power by adjusting its position in the reactor core during normal operation and should be quickly inserted into the reactor core by free drop under scram condition to shut down chain reactions. Therefore, the drop time of the CRA is one of important factors for the safety of the nuclear reactor and must be experimentally verified. This study presents the drop performance test of the CRA which has been conceptually designed for the Proto-type Generation IV Sodium-cooled Fast Reactor. During the test, the CRA was free dropped from a height of 1 m under different flow rate conditions and its drop time was measured. The results showed that the drop time of the CRA increased as the flow rate increased; the average drop times of the CRA were approximately 1.527 seconds, 1.599 seconds and 1.676 seconds at 0%, 100% and 200% of design flow rates, respectively.

Development of Vibration Absorption Device for the Transportation-Trailer System (IV) - Connecting Hitch, Leaf Spring and Shock Absorber Suspension - (수송 트레일러의 충격흡수장치 개발 (IV) - 동력경운기 적재함의 연결히치, 판스프링, 쇽업쇼바 -)

  • Hong, Jong Ho;Wu, Yong Gen
    • Journal of Biosystems Engineering
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    • v.37 no.6
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    • pp.359-364
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    • 2012
  • Purpose: This study was conducted to analyze the vibration absorption effect for the agricultural product transportation-trailer equipped with vibration absorbable connecting hitch, leaf spring suspension, and shock absorber simultaneously (HLS), comparing with the trailer equipped with vibration absorbable connecting hitch only(H), trailer equipped with connecting hitch and leaf spring suspension (HL), and existing trailer with no vibration absorption device (E). Methods: Vertical accelerations were measured at driver seat and front, middle, rear parts of trailer bottom with no load for 4 types of transportation-trailer, and analyzed using FFT analyzer. Results: The magnitude of average vibration accelerations occurred up to 20 Hz, at this low frequencies the severe damage for agricultural products could be represented, was lower (maximum 6 times) for HLS trailer compared with H trailer. And vibration absorption effect for HLS trailer was also higher up to 40-80 Hz and 80-100 Hz, but the difference was less. At driver seat, the vibration absorption effect was high severely for HL and HLS trailer, and the magnitude of vibration acceleration was showed less difference in comparing at trailer bottom. Conclusions: From the test results, it could be recommended that the agricultural products transportation trailer should be equipped with vibration absorption device of HLS.

The influence of iatrogenic mobilization in the initial stage of implant installation on final osteointegration (임플란트 식립 초기 의원성 동요가 최종 골결합에 미치는 영향)

  • Kwak, Myeong-Bae;Cho, Jin-Hyun;Lee, Du-Heong;Lee, Cheong-Hee
    • The Journal of Korean Academy of Prosthodontics
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    • v.52 no.2
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    • pp.105-112
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    • 2014
  • Purpose: The aim of present investigation was to find out the influence of several times iatrogenic mobilization in the initial stage of implant installation on bone-implant osteointegration. Materials and methods: The experimental implants (3.75 mm in diameter, 8.0 mm in length) were made of commercially pure (Grade IV) titanium, and were treated with RBM ($MegaGen^{(R)}$: Ca-P) on lower 4.0 mm part. Only lower part of implant was inserted to bone and the implants were nonsubmerged. The 130 implants (two in each tibia) were inserted into the monocortical tibias of 33 rabbits which each weighed more than 3.5 kg (Female, New Zealand White). According to the removal torque interval, the groups were divided into 13 groups, group I (1 day), group II (1 day + 2 days), group III (1 day + 2 days + 3 days), group IV (1 day + 2 days + 3 days + 4 days), group V (2 days), group VI (2 days + 4 days), group VII (2 days + 4 days + 6 days), group VIII (2 days + 4 days + 6 days + 8 days), group IX (4 days), group X (4 days + 7 days), group XI (4 days + 7 days + 10 days), group XII (4 days + 7 days + 10 days + 14 days) and control group. In the control group, the removal torque was measured at 8 weeks with a digital torque gauge (Mark-10, USA). In the experimental groups, the removal torque was given once, twice, three times or four times by experiment design before the final removal torque and the value was measured each time. The implants were then screwed back to their original positions. All the experimental groups were given a final healing time of 8 weeks after placement, in which values were compared with the control groups and the 1st, 2nd, 3rd or 4th removal torque values in each experimental group. Results: In comparison of the final removal torque tests among experimental groups, the removal torque value of experimental groups except group XII were not statistically different that of control group. And the values of group I and II were significantly higher than the values of group VI, VIII, X, XI, and XII. In addition, the values of group III, IV, and V were significantly higher than group XI and XII. In comparison of the removal torque in the each experimental group, the final removal torque were significantly higher in all groups except group VIII, X, XI, and XII. Conclusion: If sufficient healing time was allowed, a few mobilization of fixture at the very early stage after the implant placement in the rabbits didn't interrupt the final bone to implant osseointegration.

Evaluation of High Temperature Structural Integrity of Intermediate Heat Exchanger in a Steady State Condition for PGSFR (PGSFR중간열교환기의 정상상태 고온 구조 건전성 평가)

  • Lee, Seong-Hyeon;Koo, Gyeong-Hoi;Kim, Sung-Kyun
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.12 no.1
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    • pp.107-114
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    • 2016
  • Four cylindrically shaped IHXs(Intermediate Heat Exchangers) are installed in the PHTS(Primary Heat Transfer System) of the PGSFR(Prototype Gen IV Sodium cooled Fast Reactor). As for the IHX, the temperature difference of structure is inevitable result caused by heat transfer between primary coolant sodium and IHTS(Intermediate Heat Transport System) sodium. It is necessary to evaluate the high temperature structural integrity of IHXs which operate at the elevated temperature condition over the creep temperature. In this paper, the high temperature structural integrity of IHX under assumed loading conditions has been reviewed according to ASME code.

MCCARD: MONTE CARLO CODE FOR ADVANCED REACTOR DESIGN AND ANALYSIS

  • Shim, Hyung-Jin;Han, Beom-Seok;Jung, Jong-Sung;Park, Ho-Jin;Kim, Chang-Hyo
    • Nuclear Engineering and Technology
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    • v.44 no.2
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    • pp.161-176
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    • 2012
  • McCARD is a Monte Carlo (MC) neutron-photon transport simulation code. It has been developed exclusively for the neutronics design of nuclear reactors and fuel systems. It is capable of performing the whole-core neutronics calculations, the reactor fuel burnup analysis, the few group diffusion theory constant generation, sensitivity and uncertainty (S/U) analysis, and uncertainty propagation analysis. It has some special features such as the anterior convergence diagnostics, real variance estimation, neutronics analysis with temperature feedback, $B_1$ theory-augmented few group constants generation, kinetics parameter generation and MC S/U analysis based on the use of adjoint flux. This paper describes the theoretical basis of these features and validation calculations for both neutronics benchmark problems and commercial PWR reactors in operation.

Current Status and Future Prospective of Advanced Radiation Resistant Oxide Dispersion Strengthened Steel (ARROS) Development for Nuclear Reactor System Applications

  • Kim, Tae Kyu;Noh, Sanghoon;Kang, Suk Hoon;Park, Jin Ju;Jin, Hyun Ju;Lee, Min Ku;Jang, Jinsugn;Rhee, Chang Kyu
    • Nuclear Engineering and Technology
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    • v.48 no.2
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    • pp.572-594
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    • 2016
  • As one of the Gen-IV nuclear energy systems, a sodium-cooled fast reactor (SFR) is being developed at the Korea Atomic Energy Research Institute. As a long-term national research project, advanced radiation resistant oxide dispersion strengthened steel (ARROS) is being developed as an in-core fuel cladding tube material for a SFR in the future. In this paper, the current status of ARROS development is reviewed and its future prospective is discussed.

Preliminary analysis and design of the heat exchangers for the Molten Salt Fast Reactor

  • Ronco, Andrea Di;Cammi, Antonio;Lorenzi, Stefano
    • Nuclear Engineering and Technology
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    • v.52 no.1
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    • pp.51-58
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    • 2020
  • Despite the recent growth of interest in molten salt reactor technology and the crucial role which heat transfer plays in the design of power reactors, specific studies on the design of heat exchangers for the Molten Salt Fast Reactor have not yet been performed. In this work we deliver a preliminary but quantitative analysis of the intermediate heat exchangers, based on reference design data from the SAMOFAR H2020-Euratom project. Two different promising reference technologies are selected for study thanks to their compactness features, the Printed Circuit and the Helical Coil heat exchangers. We present preliminary design results for each technology, based on simplified design tools. Results highlight the limiting effects of the compactness constraints imposed on the fuel salt inventory and the allowed size. Large pressure drops on both flow sides are to be expected, with negative consequences on pumping power and natural circulation capabilities. The small size required for the flow channels also represents possible fabrication issues and safety concerns regarding channel blockage.