Preliminary Multi-Physics Performance Analysis and Design Evaluation of UO2 Fuel for LBE-Cooled Subcritical Reactor of China Initiative Accelerator Driven System

The China initiative Accelerator Driven System (CiADS) and the corresponding lead-bismuth eutectic (LBE) cooled subcritical reactor, as the research subject of one of the major national science and technology infrastructure projects, are undertaken by the Institute of Modern Physics-Chinese Academy...

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Published inFrontiers in energy research Vol. 9
Main Authors Wang, Guan, Gu, Long, Yun, Di
Format Journal Article
LanguageEnglish
Published Frontiers Media S.A 15.10.2021
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ISSN2296-598X
2296-598X
DOI10.3389/fenrg.2021.732801

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Abstract The China initiative Accelerator Driven System (CiADS) and the corresponding lead-bismuth eutectic (LBE) cooled subcritical reactor, as the research subject of one of the major national science and technology infrastructure projects, are undertaken by the Institute of Modern Physics-Chinese Academy of Sciences (IMP-CAS). And in the first phase, UO 2 fuels will be loaded in the subcritical core to test the coupling technology and achieve a long-term steady operation. A brief description of CiADS subcritical reactor, fuel assembly and fuel element are presented here, and a multi-physics performance analysis and design evaluation of CiADS UO 2 fuel are carried out by means of the FUTURE code. FUTURE is a fuel performance analysis code to evaluate the synergy of phenomena occurring in the fuel element and their impact on the fuel design improvement for the liquid metal fast reactor, which was developed jointly by IMP-CAS and Xi’an Jiaotong University (XJTU). In this paper, the FUTURE code was modified and updated focusing on characteristics of CiADS fuels. Relocation and densification models were added. Results of the hottest fuel element, mainly concerning the thermo-mechanical behaviors, are discussed concerning both fuel and cladding performance on the basis of indicative design limits. According to the preliminary design, the CiADS UO 2 fuel exhibits good performance, and the main safety parameters are far below the indicative limits. The Fuel Cladding Mechanical Interaction (FCMI) is not very serious, and the permanent cladding strains and Cumulative Damage Fraction (CDF) are small and even negligible thanks to the low level of fuel temperature and corresponding stress. However, some critical issues may still exist, especially on LBE corrosion near the coolant inlet, where protective oxide layers are very thin from BoL to EoL. The modeling is useful for providing feedback to the conceptual design of the CiADS LBE-cooled subcritical reactor and the update of FUTURE code.
AbstractList The China initiative Accelerator Driven System (CiADS) and the corresponding lead-bismuth eutectic (LBE) cooled subcritical reactor, as the research subject of one of the major national science and technology infrastructure projects, are undertaken by the Institute of Modern Physics-Chinese Academy of Sciences (IMP-CAS). And in the first phase, UO2 fuels will be loaded in the subcritical core to test the coupling technology and achieve a long-term steady operation. A brief description of CiADS subcritical reactor, fuel assembly and fuel element are presented here, and a multi-physics performance analysis and design evaluation of CiADS UO2 fuel are carried out by means of the FUTURE code. FUTURE is a fuel performance analysis code to evaluate the synergy of phenomena occurring in the fuel element and their impact on the fuel design improvement for the liquid metal fast reactor, which was developed jointly by IMP-CAS and Xi’an Jiaotong University (XJTU). In this paper, the FUTURE code was modified and updated focusing on characteristics of CiADS fuels. Relocation and densification models were added. Results of the hottest fuel element, mainly concerning the thermo-mechanical behaviors, are discussed concerning both fuel and cladding performance on the basis of indicative design limits. According to the preliminary design, the CiADS UO2 fuel exhibits good performance, and the main safety parameters are far below the indicative limits. The Fuel Cladding Mechanical Interaction (FCMI) is not very serious, and the permanent cladding strains and Cumulative Damage Fraction (CDF) are small and even negligible thanks to the low level of fuel temperature and corresponding stress. However, some critical issues may still exist, especially on LBE corrosion near the coolant inlet, where protective oxide layers are very thin from BoL to EoL. The modeling is useful for providing feedback to the conceptual design of the CiADS LBE-cooled subcritical reactor and the update of FUTURE code.
The China initiative Accelerator Driven System (CiADS) and the corresponding lead-bismuth eutectic (LBE) cooled subcritical reactor, as the research subject of one of the major national science and technology infrastructure projects, are undertaken by the Institute of Modern Physics-Chinese Academy of Sciences (IMP-CAS). And in the first phase, UO 2 fuels will be loaded in the subcritical core to test the coupling technology and achieve a long-term steady operation. A brief description of CiADS subcritical reactor, fuel assembly and fuel element are presented here, and a multi-physics performance analysis and design evaluation of CiADS UO 2 fuel are carried out by means of the FUTURE code. FUTURE is a fuel performance analysis code to evaluate the synergy of phenomena occurring in the fuel element and their impact on the fuel design improvement for the liquid metal fast reactor, which was developed jointly by IMP-CAS and Xi’an Jiaotong University (XJTU). In this paper, the FUTURE code was modified and updated focusing on characteristics of CiADS fuels. Relocation and densification models were added. Results of the hottest fuel element, mainly concerning the thermo-mechanical behaviors, are discussed concerning both fuel and cladding performance on the basis of indicative design limits. According to the preliminary design, the CiADS UO 2 fuel exhibits good performance, and the main safety parameters are far below the indicative limits. The Fuel Cladding Mechanical Interaction (FCMI) is not very serious, and the permanent cladding strains and Cumulative Damage Fraction (CDF) are small and even negligible thanks to the low level of fuel temperature and corresponding stress. However, some critical issues may still exist, especially on LBE corrosion near the coolant inlet, where protective oxide layers are very thin from BoL to EoL. The modeling is useful for providing feedback to the conceptual design of the CiADS LBE-cooled subcritical reactor and the update of FUTURE code.
Author Wang, Guan
Gu, Long
Yun, Di
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Cites_doi 10.13832/j.jnpe.2018.05.0051
10.1016/b978-0-12-803581-8.12067-3
10.1016/0022-3115(93)90193-3
10.1016/j.pnucene.2007.11.066
10.1002/er.6569
10.1016/j.egypro.2011.06.039
10.1016/s0168-9002(01)00164-4
10.1016/j.nucengdes.2014.06.032
10.1016/0029-5493(88)90292-0
10.1007/s11085-014-9469-4
10.7538/yzk.2020.youxian.0864
10.7538/yzk.2021.youxian.0343
10.1016/B978-0-12-803581-8.11690-X
10.2172/6949378
10.1016/b978-0-444-89571-4.50046-3
10.2172/1374503
10.1016/0029-5493(85)90169-4
10.1007/s11708-021-0760-1
10.2172/7343826
10.1016/j.pnucene.2014.02.010
10.1016/B978-0-12-803581-8.12049-1
10.1140/epjst/e2009-01157-8
10.1016/B978-0-12-803581-8.11693-5
10.3969/j.issn.1000-3045.2012.03.017
10.7538/yzk.2017.51.12.2235
10.1016/j.anucene.2012.03.021
10.1007/s11085-013-9450-7
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References Delage (B7) 2011; 7
Olander (B25) 1976
Wang (B35) 2021
Rubbia (B30) 1995
Xu (B36) 2015; 25
Lanning (B17) 1978
Delage (B6) 2020
Fletcher (B9) 1992
Yu (B37) 2021; 45
Zhang (B40) 2014; 81
Garner (B10) 2020
Abderrahim (B1) 2001; 463
Siefken (B31) 1985; 88
Kelly (B15) 2014; 77
Carbol (B5) 2012
Zhang (B41) 2018; 39
(B24) 2002
Többe (B32) 1975
Wade (B34) 2000
Waltar (B42) 2011
Maschek (B22) 2008; 50
Rashid (B28) 2004
Hales (B13) 2016
Liu (B20) 2021
(B4) 2003
Zhan (B38) 2012; 27
Lassmann (B19) 1992; 188
Baetslé (B3) 1988
Rossi (B29) 2006
Lassmann (B18) 1988; 106
Peng (B27) 2017; 51
Ahmad (B2) 2012; 46
Pelletier (B26) 2020
Grasso (B11) 2013
Kittel (B16) 1993; 204
Mueller (B23) 2009; 176
Luzzi (B21) 2014; 277
Zhang (B39) 2013; 80
Filacchioni (B8) 1990
Van Uffelen (B33) 2020
(B14) 2015
Gu (B12) 2021
References_xml – volume: 39
  start-page: 51
  year: 2018
  ident: B41
  article-title: Safety Analysis of CiADS Sub-critical Reactor Fuel Cladding under Beam Transients
  publication-title: Nucl. Power Eng.
  doi: 10.13832/j.jnpe.2018.05.0051
– year: 2006
  ident: B29
  article-title: MATPRO: a Computer Library of Material Property at Cryogenic Temperature
  publication-title: J. Care-note--018-hhh, Supercond. Database
– year: 1988
  ident: B3
  article-title: Status and Assessment Report on Actinide and Fission Product Partitioning and Transmutation
– start-page: 57
  year: 2020
  ident: B10
  article-title: Radiation-Induced Damage in Austenitic Structural Steels Used in Nuclear Reactors
  publication-title: Comprehensive Nuclear Materials
  doi: 10.1016/b978-0-12-803581-8.12067-3
– volume: 204
  start-page: 1
  year: 1993
  ident: B16
  article-title: History of Fast Reactor Fuel Development
  publication-title: J. Nucl. Mater.
  doi: 10.1016/0022-3115(93)90193-3
– volume: 50
  start-page: 333
  year: 2008
  ident: B22
  article-title: Accelerator Driven Systems for Transmutation: Fuel Development, Design and Safety
  publication-title: J. Prog. Nucl. Energ.
  doi: 10.1016/j.pnucene.2007.11.066
– volume: 45
  start-page: 11552
  year: 2021
  ident: B37
  article-title: Review of Fuel Assembly Design in lead‐based Fast Reactors and Research Progress in Fuel Assembly of China Initiative Accelerator Driven System
  publication-title: Int. J. Energ. Res.
  doi: 10.1002/er.6569
– volume-title: Status and Advances in MOX Fuel Technology
  year: 2003
  ident: B4
– volume: 7
  start-page: 303
  year: 2011
  ident: B7
  article-title: ADS Fuel Developments in Europe: Results from the EUROTRANS Integrated Project
  publication-title: Energ. Proced.
  doi: 10.1016/j.egypro.2011.06.039
– volume: 463
  start-page: 487
  year: 2001
  ident: B1
  article-title: MYRRHA: A Multipurpose Accelerator Driven System for Research & Development
  publication-title: Nucl. Instr. Methods Phys. Res. Sect. A: Acc. Spect. Detect. Assoc. Equip.
  doi: 10.1016/s0168-9002(01)00164-4
– volume-title: J Reference Module In Materials Science Materials Engineering
  year: 2012
  ident: B5
  article-title: Spent Nuclear Fuel as Waste Material
– volume: 277
  start-page: 173
  year: 2014
  ident: B21
  article-title: Application of the TRANSURANUS Code for the Fuel Pin Design Process of the ALFRED Reactor
  publication-title: Nucl. Eng. Des.
  doi: 10.1016/j.nucengdes.2014.06.032
– volume-title: Conceptual Design of a Fast Neutron Operated High Power Energy Amplifier
  year: 1995
  ident: B30
– volume: 25
  year: 2015
  ident: B36
  article-title: China's Accelerator Driven Sub-critical System (ADS) Program
  publication-title: J. Aapps Bull.
– volume: 106
  start-page: 291
  year: 1988
  ident: B18
  article-title: Modelling of Fuel Rod Behaviour and Recent Advances of the Transuranus Code
  publication-title: Nucl. Eng. Des.
  doi: 10.1016/0029-5493(88)90292-0
– volume-title: Fast Spectrum Reactors
  year: 2011
  ident: B42
– volume: 81
  start-page: 597
  year: 2014
  ident: B40
  article-title: Long-Term Behaviors of Oxide Layer in Liquid Lead–Bismuth Eutectic (LBE), Part II: Model Applications
  publication-title: Oxid. met.
  doi: 10.1007/s11085-014-9469-4
– year: 2021
  ident: B20
  article-title: Development and Verification of a Subchannel Code for lead Cooled Fast Reactor Fuel Assembly with Wire Spacers
  publication-title: J. At. Energ. Sci. Technol.
  doi: 10.7538/yzk.2020.youxian.0864
– volume-title: Status of Accelerator Driven Systems Research and Technology Development
  year: 2015
  ident: B14
– volume-title: J Proceedings of Fast Reactors Related Fuel Cycles
  year: 2013
  ident: B11
  article-title: Demonstrating the Effectiveness of the European LFR Concept: the ALFRED Core Design
– year: 2021
  ident: B35
  article-title: Development and Preliminary Verification of Oxide Fuel Performance Analysis Code FUTURE for Lead-based Fast Reactor
  publication-title: J Atomic Energy Science Technology
  doi: 10.7538/yzk.2021.youxian.0343
– start-page: 72
  volume-title: Comprehensive Nuclear Materials
  year: 2020
  ident: B26
  article-title: Fuel Performance of Fast Spectrum Oxide Fuel
  doi: 10.1016/B978-0-12-803581-8.11690-X
– volume-title: GAPCON-THERMAL-3 Code Description
  year: 1978
  ident: B17
  doi: 10.2172/6949378
– volume: 188
  start-page: 295
  year: 1992
  ident: B19
  article-title: TRANSURANUS: a Fuel Rod Analysis Code Ready for Use
  publication-title: J. Nucl. Mater.
  doi: 10.1016/b978-0-444-89571-4.50046-3
– volume-title: Information Meeting on Actinide and Fission Product Partitioning & Transmutation
  year: 2000
  ident: B34
  article-title: Safety Considerations in Design of Fast Spectrum ADS for Transuranic or Minor Actinide Burning: A Status Report on Activities of the OECD-NEA Expert Group
– volume-title: BISON Theory Manual the Equations behind Nuclear Fuel Analysis
  year: 2016
  ident: B13
  doi: 10.2172/1374503
– volume: 88
  start-page: 341
  year: 1985
  ident: B31
  article-title: FRAP-T6: A Computer Code for the Transient Analysis of Oxide Fuel Rods
  publication-title: Nucl. Eng. Des.
  doi: 10.1016/0029-5493(85)90169-4
– start-page: 1
  year: 2021
  ident: B12
  article-title: Latest Research Progress for LBE Coolant Reactor of China Initiative Accelerator Driven System Project
  publication-title: J. Front. Energ.
  doi: 10.1007/s11708-021-0760-1
– volume-title: Fundamental Aspects of Nuclear Reactor Fuel Elements: Solutions to Problems
  year: 1976
  ident: B25
  doi: 10.2172/7343826
– volume: 77
  start-page: 240
  year: 2014
  ident: B15
  article-title: Generation IV International Forum: A Decade of Progress through International Cooperation
  publication-title: Prog. Nucl. Energ.
  doi: 10.1016/j.pnucene.2014.02.010
– volume-title: Actinide-Bearing Fuels and Transmutation Targets
  year: 2020
  ident: B6
  doi: 10.1016/B978-0-12-803581-8.12049-1
– start-page: 255
  volume-title: Fast Reactor Core and Fuel Structural Behaviour
  year: 1990
  ident: B8
  article-title: Mechanical and Structural Behaviour of the Second Double Stabilized Stainless Steels Generation
– volume: 176
  start-page: 179
  year: 2009
  ident: B23
  article-title: Prospects for Transmutation of Nuclear Waste and Associated Proton-Accelerator Technology
  publication-title: Eur. Phys. J. Spec. Top.
  doi: 10.1140/epjst/e2009-01157-8
– year: 2004
  ident: B28
  article-title: Fuel Analysis and Licensing Code: FALCON MOD01
– start-page: 363
  volume-title: Comprehensive Nuclear Materials
  year: 2020
  ident: B33
  article-title: Oxide Fuel Performance Modeling and Simulation
  doi: 10.1016/B978-0-12-803581-8.11693-5
– year: 1975
  ident: B32
  article-title: Das Brennstabrechenprogramm IAMBUS zur Auslegung von Schnellbrüter-Brennstäben
  publication-title: J. Interatom. Technischer Bericht.
– volume: 27
  start-page: 375
  year: 2012
  ident: B38
  article-title: Advanced Fission Energy Program-ADS Transmutation System
  publication-title: J. Bull. Chin. Acad. Sci.
  doi: 10.3969/j.issn.1000-3045.2012.03.017
– volume: 51
  start-page: 2235
  year: 2017
  ident: B27
  article-title: Conceptual Design of Subcritical Reactor for China Initiative Accelerator Driven System
  publication-title: J. At. Energ. Sci. Technol.
  doi: 10.7538/yzk.2017.51.12.2235
– year: 1992
  ident: B9
  article-title: RELAP5/MOD3 Code Manual
  publication-title: Nucl. Regul. Comm.
– volume-title: Advanced Nuclear Fuel Cycles. A Comparative Study
  year: 2002
  ident: B24
  article-title: Accelerator-Driven Systems (ADS) and Fast Reactors (FR)
– volume: 46
  start-page: 97
  year: 2012
  ident: B2
  article-title: The Effect of Beam Interruptions on the Integrity of ADSR Fuel Pin Cladding: A Thermo-Mechanical Analysis
  publication-title: Ann. Nucl. Energ.
  doi: 10.1016/j.anucene.2012.03.021
– volume: 80
  start-page: 669
  year: 2013
  ident: B39
  article-title: Long-term Behaviors of Oxide Layer in Liquid lead–bismuth Eutectic (LBE), Part I: Model Development and Validation
  publication-title: Oxid. met.
  doi: 10.1007/s11085-013-9450-7
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SubjectTerms CiADS
FUTURE code
LBE
performance analysis
subcritical reactor
UO2 fuel
Title Preliminary Multi-Physics Performance Analysis and Design Evaluation of UO2 Fuel for LBE-Cooled Subcritical Reactor of China Initiative Accelerator Driven System
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