[논문]On the feasibility of duplex stainless steel 2205 as an accident tolerant fuel cladding material for light water reactors

Xiao, Qian; Kim, Chaewon; Jang, Changheui; Jeong, Chaewon; Kim, Hyunmyung; Chen, Junjie; Heo, Woong

doi:10.1016/j.jnucmat.2021.153265

[해외논문] On the feasibility of duplex stainless steel 2205 as an accident tolerant fuel cladding material for light water reactors

Journal of nuclear materials = Journal des matériaux nucléaires, v.557, 2021년, pp.153265 -

Xiao, Qian (Korea Advanced Institute of Science and Technology) , Kim, Chaewon (Korea Advanced Institute of Science and Technology) , Jang, Changheui (Korea Advanced Institute of Science and Technology) , Jeong, Chaewon (Korea Advanced Institute of Science and Technology) , Kim, Hyunmyung (Korea Atomic Energy Research Institute) , Chen, Junjie (Korea Advanced Institute of Science and Technology) , Heo, Woong (Korea Advanced Institute of Science and Technology)

Abstract ▼ AI-Helper

Abstract A few tests were performed to evaluate the feasibility of 2205 duplex stainless steel (DSS) as an accident tolerant fuel (ATF) cladding material, including corrosion tests in simulated pressure water reactor (PWR) primary water and high-temperature steam, stress corrosion cracking (SCC) initiation test, mechanical properties test and thermal aging effects. In both 360 °C PWR primary water and 1200 °C steam, DSS 2205 showed weight changes comparable to the high-Cr alloys. After 3163 h of exposure in 400 °C steam, U-bend specimens of DSS 2205 showed no obvious cracks, suggesting that SCC is not likely to be initiated during the service life. Compared to FeCrAl alloys, DSS 2205 showed comparable strength but greater ductility. Though 400 °C thermal aging caused an increase in strength for DSS 2205, total elongation was more than 35% even after 11,061 h aging, greater than other Fe-based ATF alloys. Also, concerns on neutron penalty, irradiation, fabrication and spent fuel storage were discussed. The overall results suggest that DSS 2205 could be considered as a candidate ATF cladding material.

Keyword

참고문헌 (53)

Rebak 2020 Accident-Tolerant Materials for Light Water Reactor Fuels
J. Nucl. Mater. Zinkle 448 374 2014 10.1016/j.jnucmat.2013.12.005 Accident tolerant fuels for LWRs: a perspective

상세보기
J. Nucl. Mater. Terrani 501 13 2018 10.1016/j.jnucmat.2017.12.043 Accident tolerant fuel cladding development: promise, status, and challenges

상세보기
J. Nucl. Mater. Yamamoto 467 703 2015 10.1016/j.jnucmat.2015.10.019 Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors

상세보기
J. Nucl. Mater. Kim 507 1 2018 10.1016/j.jnucmat.2018.04.027 Development of alumina-forming duplex stainless steels as accident-tolerant fuel cladding materials for light water reactors

상세보기
J. Mater. Process. Technol. Huang 277 2020 10.1016/j.jmatprotec.2019.116434 Cold-rolling & annealing process for nuclear grade wrought FeCrAl cladding alloy to enhance the strength and ductility

상세보기
Int. J. Energy Res. Kim 44 8074 2020 10.1002/er.5021 Feasibility assessment of the alumina-forming duplex stainless steels as accident tolerant fuel cladding materials for light water reactors

상세보기
Acta Mater. Zinkle 61 735 2013 10.1016/j.actamat.2012.11.004 Materials challenges in nuclear energy

상세보기
EPJ Nucl. Sci. Technol. Rebak 3 34 2017 10.1051/epjn/2017029 Iron-chrome-aluminum alloy cladding for increasing safety in nuclear power plants

상세보기
10.2172/1214036 Y. Yamamoto, M.N. Gussev, B. Kim, T.S. Byun, Optimized properties on base metal and thin-walled tube of generation II ATF FeCrAl, Oak Ridge National Lab. Report: ORNL/TM-2015/414, 2015.
10.2172/1325688 S.A. Maloy, E. Aydogan, O. Anderoglu, C. Lavender, Y. Yamamoto, Viability of thin wall tube forming of ATF FeCrAl, Los Alamos National Lab. Report: LA-UR-15-27348, 2016.
10.2172/1214517 Y. Yamamoto, Development and quality assessments of commercial heat production of ATF FeCrAl tubes, Oak Ridge National Lab. Report: ORNL/TM-2015/478, 2015.
Gunn 1997 Duplex Stainless Steels: Microstructure, Properties and Applications
J. Adv. Res. Vinoth Jebaraj 8 183 2017 10.1016/j.jare.2017.01.002 Weldability, machinability and surfacing of commercial duplex stainless steel AISI2205 for marine applications-a recent review

상세보기
Acta Mater. Tucker 87 15 2015 10.1016/j.actamat.2014.12.012 Assessment of thermal embrittlement in duplex stainless steels 2003 and 2205 for nuclear power applications

상세보기
Corros. Sci. Della Rovere 68 84 2013 10.1016/j.corsci.2012.10.038 Influence of long-term low-temperature aging on the microhardness and corrosion properties of duplex stainless steel

상세보기
Corros. Sci. Silva 116 66 2017 10.1016/j.corsci.2016.12.014 Thermal aging at 475 °C of newly developed lean duplex stainless steel 2404: mechanical properties and corrosion behavior

상세보기
Mater. Sci. Eng. A Xu 754 512 2019 10.1016/j.msea.2019.03.046 Nanostructure, microstructure and mechanical properties of duplex stainless steels 25Cr-7 Ni and 22Cr-5Ni (wt.%) aged at 325 °C

상세보기
Mater. Sci. Eng. A Chandra 527 3904 2010 10.1016/j.msea.2010.02.069 Low temperature embrittlement of duplex stainless steel: correlation between mechanical and electrochemical behavior

상세보기
Mater. Sci. Eng. A Weng 379 119 2004 10.1016/j.msea.2003.12.051 The low-temperature aging embrittlement in a 2205 duplex stainless steel

상세보기
Sandvik SAF 2205 seamless tube and pipe. https://www.materials.sandvik/en/materials-center/material-datasheets/tube-and-pipe-seamless/saf-2205/.
J. Nucl. Mater. Fan 544 2021 10.1016/j.jnucmat.2020.152693 Thermal aging behaviors of duplex stainless steels used in nuclear power plant: a review

상세보기
J. Nucl. Mater. Yamada 350 47 2006 10.1016/j.jnucmat.2005.11.008 Mechanical property and microstructural change by thermal aging of SCS14A cast duplex stainless steel

상세보기
Mater. Sci. Eng. A Li 625 186 2015 10.1016/j.msea.2014.11.065 Effects of ferrite content on the mechanical properties of thermal aged duplex stainless steels

상세보기
Mater. Sci. Eng. A Chandra 534 163 2012 10.1016/j.msea.2011.11.055 Low temperature thermal aging of austenitic stainless steel welds: kinetics and effects on mechanical properties

상세보기
Mater. Sci. Eng. A Kim 743 159 2019 10.1016/j.msea.2018.11.084 400 °C aging embrittlement of FeCrAl alloys: microstructure and fracture behavior

상세보기
J. Nucl. Mater. Terrani 479 36 2016 10.1016/j.jnucmat.2016.06.047 Uniform corrosion of FeCrAl alloys in LWR coolant environments

상세보기
Corros. Sci. Xiao 2020 10.1016/j.corsci.2020.108991 Corrosion behavior of stainless steels in simulated PWR primary water: the effect of composition and matrix phases

상세보기
J. Nucl. Mater. Pint 440 420 2013 10.1016/j.jnucmat.2013.05.047 High temperature oxidation of fuel cladding candidate materials in steam-hydrogen environments

상세보기
JOM Rebak 70 1484 2018 10.1007/s11837-018-2979-9 Oxidation characteristics of two FeCrAl alloys in air and steam from 800°C to 1300°C

상세보기
Corros. Sci. Park 94 459 2015 10.1016/j.corsci.2015.02.027 A study of the oxidation of FeCrAl alloy in pressurized water and high-temperature steam environment

상세보기
Int. J. Miner. Metall. Mater. Liu 25 1148 2018 10.1007/s12613-018-1666-8 Mechanical properties and kinetics of thermally aged Z3CN20.09M cast duplex stainless steel

상세보기
Nucl. Eng. Des. Kawaguchi 174 273 1997 10.1016/S0029-5493(97)00126-X Microstructural changes and fracture behavior of CF8M duplex stainless steels after long-term aging

상세보기
Ann. Nucl. Energy Naceur 113 147 2018 10.1016/j.anucene.2017.11.016 Neutronic analysis for accident tolerant cladding candidates in CANDU-6 reactors

상세보기
J. Nucl. Mater. Garner 258-263 1740 1998 10.1016/S0022-3115(98)00297-9 The dependence of helium generation rate on nickel content of Fe-Cr-Ni alloys irradiated to high dpa levels in EBR-II

상세보기
Scr. Mater. Hsieh 125 44 2016 10.1016/j.scriptamat.2016.06.047 In-situ transmission electron microscopy investigation of the deformation behavior of spinodal nanostructured δ-ferrite in a duplex stainless steel

상세보기
Periodic Table of Elements, Sorted by Cross Section (Thermal Neutron Capture). https://environmentalchemistry.com/yogi/periodic/crosssection.html.
J. Nucl. Mater. Terrani 448 420 2014 10.1016/j.jnucmat.2013.06.041 Advanced oxidation-resistant iron-based alloys for LWR fuel cladding

상세보기
J. Nucl. Mater. Field 489 118 2017 10.1016/j.jnucmat.2017.03.038 Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys

상세보기
J. Nucl. Mater. Chopra 412 195 2011 10.1016/j.jnucmat.2011.02.059 A review of irradiation effects on LWR core internal materials - neutron embrittlement

상세보기
J. Nucl. Mater. Chopra 409 235 2011 10.1016/j.jnucmat.2010.12.001 A review of irradiation effects on LWR core internal materials - IASCC susceptibility and crack growth rates of austenitic stainless steels

상세보기
Sandvik, Stainless tubular products stock program, 2013. https://applicatie.verum.nl/files/3414/0784/5193/S-004-ENG_114_Sandvik.pdf.
Duplex 2205 Tubing and Duplex Heat Exchanger Tubes Manufacturer in Mumbai, India. https://www.duplexpipes.com/duplex-stainless-steel-seamless-tube.html.
Int. J. Adv. Manuf. Technol. Na 98 2241 2018 10.1007/s00170-018-2365-3 A study on characteristics of end plug resistance welding process in nuclear fuel rods by experiment and numerical simulation

상세보기
JOM Gan 70 192 2018 10.1007/s11837-017-2697-8 Laser and pressure resistance weld of thin-wall cladding for LWR accident-tolerant fuels

상세보기
Oper. Appl. Compon. Am. Soc. Mech. Eng. Rebak 7 2015 Anticipated improved performance of advanced steel cladding under long term dry storage of spent fuel
J. Nucl. Mater. Xiao 548 2021 10.1016/j.jnucmat.2021.152845 Corrosion behavior of Fe-based candidate accident tolerant fuel cladding alloys in spent fuel pool environment - effect of prior corrosion

상세보기
ECS Trans. Motooka 53 25 2013 10.1149/05321.0025ecst Pitting potential of zircaloy-2 in artificial seawater under gamma-ray irradiation

상세보기
J. Nucl. Mater. Lavigne 426 120 2012 10.1016/j.jnucmat.2012.03.036 On the corrosion behavior of zircaloy-4 in spent fuel pools under accidental conditions

상세보기
Electrochim. Acta Deng 53 5220 2008 10.1016/j.electacta.2008.02.047 Critical pitting and repassivation temperatures for duplex stainless steel in chloride solutions

상세보기
Am. Nucl. Soc. Global Rebak 1056 2019 Localized corrosion behavior of FeCrAl nuclear fuel cladding in pool storage
Rebak 12944 2019 Corrosion evaluation of iron-chromium-aluminum alloys in used fuel cooling pools
Acta Mater. Chen 197 172 2020 10.1016/j.actamat.2020.07.046 Evaluation of pitting corrosion in duplex stainless steel Fe20Cr9Ni for nuclear power application

상세보기

LOADING...

활용도 분석정보

상세보기

다운로드

내보내기

활용도 Top5 논문

해당 논문의 주제분야에서 활용도가 높은 상위 5개 콘텐츠를 보여줍니다.
더보기 버튼을 클릭하시면 더 많은 관련자료를 살펴볼 수 있습니다.

원문 URL 링크

DOI : 10.1016/j.jnucmat.2021.153265
Elsevier : 저널 > 논문

*원문 PDF 파일 및 링크정보가 존재하지 않을 경우 KISTI DDS 시스템에서 제공하는 원문복사서비스를 사용할 수 있습니다.

저작권 관리 안내

내보내기 메뉴

내보내기 구분

파일저장
인쇄
메일전송

구성항목

기본정보
상세정보

관리번호, 논문명, 저널/프로시딩명, 저자 , 발행년, 권, 호, 시작페이지, 끝페이지, 발행기관

저장형식

Text(ASCII format)
Excel format
RefWorks Direct Export
RIS format (for Reference Manager, ProCite, EndNote), Scholar's Aids, Mendeley

메일정보

받는사람 (필수): @
보내는사람 (선택): @
제목
내용: KISTI 검색결과 이메일 서비스

안내

총 건의 자료가 검색되었습니다.

다운받으실 자료의 인덱스를 입력하세요. (1-10,000)

검색결과의 순서대로 최대 10,000건 까지 다운로드가 가능합니다.

데이타가 많을 경우 속도가 느려질 수 있습니다.(최대 2~3분 소요)

다운로드 파일은 UTF-8 형태로 저장됩니다.
파일의 내용이 제대로 보이지 않을실 때는 웹브라우저 상단의 보기 -> 인코딩 -> 자동선택 여부를 확인하십시오.

Text(ASCII format)
Excel format

표제어: PCR

동의어: Packet Collision Rate

용어 설명 출처 목록 (6)

용어 설명: PCR은 세균 특이성이 있는 primer를 이용하여 적은 수의 세균이 있을지라도 쉽게 검출할 수 있는 유용한 방법이며, 이를 이용하여 구강 내 치면세균막이나 타액에서 직접 세균을 검출할 수 있게 되었다[8].

AI-Helper ※ AI-Helper는 을 사용합니다.

AI-Helper

안녕하세요, AI-Helper입니다. 좌측 "선택된 텍스트"에서 텍스트를 선택하여 요약, 번역, 용어설명을 실행하세요.
※ AI-Helper는 부적절한 답변을 할 수 있습니다.

연합인증