Preparation and verification of mixed high-energy neutron crosssection library for ADS
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摘要
An accelerator-driven subcritical system(ADS)is driven by an external spallation neutron source, which is generated from a heavy metal spallation target to maintain stable operation of the subcritical core, where the energy of the spallation neutrons can reach several hundred megaelectron volts. However, the upper neutron energy limit of nuclear cross-section databases, which are widely used in critical reactor physics calculations, is generally 20 MeV.This is not suitable for simulating the transport of highenergy spallation neutrons in the ADS. We combine the Japanese JENDL-4.0/HE high-energy evaluation database and the ADS-HE and ADS 2.0 libraries from the International Atomic Energy Agency and process all the data files for nuclides with energies greater than 20 MeV. We use the continuous pointwise cross-section program NJOY2016 to generate the ACE-formatted cross-section data library IMPC-ADS at multiple temperature points. Using the IMPC-ADS library, we calculate 10 critical benchmarks of the International Criticality Safety Benchmark Evaluation Project manual, the 14-MeV fixed-source problem of the Godiva sphere, and the neutron flux of the ADS subcritical core by MCNPX. To verify the correctness of the IMPCADS, the results were compared with those calculated using the ENDF/B-VII.0 library. The results showed thatthe IMPC-ADS is reliable in effective multiplication factor and neutron flux calculations, and it can be applied to physical analysis of the ADS subcritical reactor core.
An accelerator-driven subcritical system(ADS)is driven by an external spallation neutron source, which is generated from a heavy metal spallation target to maintain stable operation of the subcritical core, where the energy of the spallation neutrons can reach several hundred megaelectron volts. However, the upper neutron energy limit of nuclear cross-section databases, which are widely used in critical reactor physics calculations, is generally 20 MeV.This is not suitable for simulating the transport of highenergy spallation neutrons in the ADS. We combine the Japanese JENDL-4.0/HE high-energy evaluation database and the ADS-HE and ADS 2.0 libraries from the International Atomic Energy Agency and process all the data files for nuclides with energies greater than 20 MeV. We use the continuous pointwise cross-section program NJOY2016 to generate the ACE-formatted cross-section data library IMPC-ADS at multiple temperature points. Using the IMPC-ADS library, we calculate 10 critical benchmarks of the International Criticality Safety Benchmark Evaluation Project manual, the 14-MeV fixed-source problem of the Godiva sphere, and the neutron flux of the ADS subcritical core by MCNPX. To verify the correctness of the IMPCADS, the results were compared with those calculated using the ENDF/B-VII.0 library. The results showed thatthe IMPC-ADS is reliable in effective multiplication factor and neutron flux calculations, and it can be applied to physical analysis of the ADS subcritical reactor core.
An accelerator-driven subcritical system(ADS)is driven by an external spallation neutron source, which is generated from a heavy metal spallation target to maintain stable operation of the subcritical core, where the energy of the spallation neutrons can reach several hundred megaelectron volts. However, the upper neutron energy limit of nuclear cross-section databases, which are widely used in critical reactor physics calculations, is generally 20 MeV.This is not suitable for simulating the transport of highenergy spallation neutrons in the ADS. We combine the Japanese JENDL-4.0/HE high-energy evaluation database and the ADS-HE and ADS 2.0 libraries from the International Atomic Energy Agency and process all the data files for nuclides with energies greater than 20 MeV. We use the continuous pointwise cross-section program NJOY2016 to generate the ACE-formatted cross-section data library IMPC-ADS at multiple temperature points. Using the IMPC-ADS library, we calculate 10 critical benchmarks of the International Criticality Safety Benchmark Evaluation Project manual, the 14-MeV fixed-source problem of the Godiva sphere, and the neutron flux of the ADS subcritical core by MCNPX. To verify the correctness of the IMPCADS, the results were compared with those calculated using the ENDF/B-VII.0 library. The results showed thatthe IMPC-ADS is reliable in effective multiplication factor and neutron flux calculations, and it can be applied to physical analysis of the ADS subcritical reactor core.
引文
1.P.F.Rose,ENDF-201,ENDF/B-VI summary documentation,Brookhaven National Laboratory,BNL-NCS-17541(1991)
2.C.L.Dunford.Cross section evaluation working group highlights.Paper presented at 12th Meeting of the Working Party on International Nuclear Data Evaluation Co-Operation.Tokai,Japan,20-21 June 2000
3.R.Jacqmin,R.Forrest,J.Rowlands et al.,Status of the JEFF-3Project.J.Nucl.Sci.Technol.39,54-55(2002).https://doi.org/10.1080/00223131.2002.10875038
4.A.V.Ignatyuk,B.I.Fursov,The latest BROND-3 developments.Paper Presented at International Conference on Nuclear Data for Science and Technology 2007.Nice,France,22-27 April 2007
5.T.Nakagawa,K.Shibata,S.Chiba et al.,Japanese evaluated nuclear data library version 3 revision-2:JENDL-3.2.J.Nucl.Sci.Technol.32,1259-1271(1995).https://doi.org/10.1080/18811248.2002.9715303
6.T.J.Liu,Present status of CENDL-3.Paper Presented at 12th Meeting of the Working Party on International Nuclear Data Evaluation Co-Operation.Tokai,Japan,20-21 June 2000
7.R.E.MacFarlane,D.W.Muir,The NJOY Nuclear Data Processing System-Version 91(Los Alamos National Laboratory,Los Alamos,1994)
8.C.D.Bowman,E.D.Arthur,P.W.Lisowski et al.,Nuclear energy generation and waste transmutation using an accelerator-driven intense thermal neutron source.Nucl.Instrum.Methods A 320,336-367(1992).https://doi.org/10.1016/0168-9002(92)90795-6
9.W.L.Zhan,H.S.Xu,Advanced fission energy program-ADStransmutation system.Bull.Chin.Acad.Sci.27,375-381(2012).https://doi.org/10.3969/j.issn.1000-3045.2012.03.017
10.X.Z.Li,H.C.Wu,Y.Q.Zheng et al.,Development and application of high-energy nuclear data library for accelerator driven sub-critical system.Atom.Energy Sci.Technol.49,371-376(2015).https://doi.org/10.7538/yzk.2015.49.S0.0371
11.S.Kunieda,O.Iwamoto,N.Iwamoto et al.,Overview of JENDL-4.0/HE and benchmark calculation.Paper Presented at Proceedings of the 2015 Symposium on Nuclear Data.Ibaraki,Japan,19-20 November 2015
12.A.Trkov,M.Herman,D.A.Brown,ENDF-6 Formats Manuals.Brookhaven National Laboratory,BNL-90365-2009 Rev.2(2011)
13.S.Kunieda,O.Iwamoto,N.Iwamoto et al.,High-energy nuclear data library JENDL-4.0/HE.Paper Presented at Proceedings of the 2015 Symposium on Nuclear Data.Ibaraki,Japan,19-20November 2015
14.D.L.Aldama,ADS-HE:Evaluated Nuclear Data Library up to1 GeV for202Hg,208Pb,209Bi,232Th,235U,238U,237Np,239Pu,242Am and245Cm.International Atomic Energy Agency/Nuclear Data Section,INDC(NDC-0656)(2013)
15.M.B.Chadwick,M.Herman,P.Oblozinsky et al.,ENDF/B-VII.1nuclear data for science and technology:cross sections,covariances,fission product yields and decay data.Nucl.Data.Sheets112,2887-2996(2011).https://doi.org/10.1016/j.nds.2011.11.002
16.K.Shibata,O.Wamoto,T.Nakagawa et al.,JENDL-4.0:a new library for nuclear science and engineering.J.Nucl.Sci.Technol.48,1-30(2011).https://doi.org/10.1080/18811248.2011.9711675
17.D.L.Aldama,A.L.Nichols.ADS-2.0 A Test Library for Accelerators Driven Systems and New Reactor Design,International Atomic Energy Agency/Nuclear Data Section,INDC(NDS)-0545(2008)
18.A.C.Kahler,The NJOY Nuclear Data Processing System,Version 2016(Los Alamos National Security,Los Alamos,2016)
19.D.B.Pelowitz,MCNPX User’s Manual,Version 2.7.0(Los Alamos National Laboratory,Los Alamos,2011)
20.J.B.Blair,A.T.Michaelat,R.Yolanda et al.,International Handbook of Evaluated Criticality Safety Benchmark Experiments,NEA/NSC/DOC(95)03(2006)
21.M.B.Chadwick,P.Oblozinsky,M.Herman et al.,ENDF/B-VII.0:next generation evaluated nuclear data library for nuclear science and technology.Nucl.Data.Sheets 107,2931-3060(2006).https://doi.org/10.1016/j.nds.2006.11.001
22.S.C.Frankle,A Suite of Criticality Benchmarks for Validating Nuclear Data.Los Alamos National Laboratory,LA-13594(1999)
23.S.Hong,Y.W.Yang,L.Zhang et al.,Fabrication and validation of multigroup cross section library based on the OpenMC code.Nucl.Tech.40,43-48(2017).https://doi.org/10.11889/j.0253-3219.2017.hjs.40.040502
2.C.L.Dunford.Cross section evaluation working group highlights.Paper presented at 12th Meeting of the Working Party on International Nuclear Data Evaluation Co-Operation.Tokai,Japan,20-21 June 2000
3.R.Jacqmin,R.Forrest,J.Rowlands et al.,Status of the JEFF-3Project.J.Nucl.Sci.Technol.39,54-55(2002).https://doi.org/10.1080/00223131.2002.10875038
4.A.V.Ignatyuk,B.I.Fursov,The latest BROND-3 developments.Paper Presented at International Conference on Nuclear Data for Science and Technology 2007.Nice,France,22-27 April 2007
5.T.Nakagawa,K.Shibata,S.Chiba et al.,Japanese evaluated nuclear data library version 3 revision-2:JENDL-3.2.J.Nucl.Sci.Technol.32,1259-1271(1995).https://doi.org/10.1080/18811248.2002.9715303
6.T.J.Liu,Present status of CENDL-3.Paper Presented at 12th Meeting of the Working Party on International Nuclear Data Evaluation Co-Operation.Tokai,Japan,20-21 June 2000
7.R.E.MacFarlane,D.W.Muir,The NJOY Nuclear Data Processing System-Version 91(Los Alamos National Laboratory,Los Alamos,1994)
8.C.D.Bowman,E.D.Arthur,P.W.Lisowski et al.,Nuclear energy generation and waste transmutation using an accelerator-driven intense thermal neutron source.Nucl.Instrum.Methods A 320,336-367(1992).https://doi.org/10.1016/0168-9002(92)90795-6
9.W.L.Zhan,H.S.Xu,Advanced fission energy program-ADStransmutation system.Bull.Chin.Acad.Sci.27,375-381(2012).https://doi.org/10.3969/j.issn.1000-3045.2012.03.017
10.X.Z.Li,H.C.Wu,Y.Q.Zheng et al.,Development and application of high-energy nuclear data library for accelerator driven sub-critical system.Atom.Energy Sci.Technol.49,371-376(2015).https://doi.org/10.7538/yzk.2015.49.S0.0371
11.S.Kunieda,O.Iwamoto,N.Iwamoto et al.,Overview of JENDL-4.0/HE and benchmark calculation.Paper Presented at Proceedings of the 2015 Symposium on Nuclear Data.Ibaraki,Japan,19-20 November 2015
12.A.Trkov,M.Herman,D.A.Brown,ENDF-6 Formats Manuals.Brookhaven National Laboratory,BNL-90365-2009 Rev.2(2011)
13.S.Kunieda,O.Iwamoto,N.Iwamoto et al.,High-energy nuclear data library JENDL-4.0/HE.Paper Presented at Proceedings of the 2015 Symposium on Nuclear Data.Ibaraki,Japan,19-20November 2015
14.D.L.Aldama,ADS-HE:Evaluated Nuclear Data Library up to1 GeV for202Hg,208Pb,209Bi,232Th,235U,238U,237Np,239Pu,242Am and245Cm.International Atomic Energy Agency/Nuclear Data Section,INDC(NDC-0656)(2013)
15.M.B.Chadwick,M.Herman,P.Oblozinsky et al.,ENDF/B-VII.1nuclear data for science and technology:cross sections,covariances,fission product yields and decay data.Nucl.Data.Sheets112,2887-2996(2011).https://doi.org/10.1016/j.nds.2011.11.002
16.K.Shibata,O.Wamoto,T.Nakagawa et al.,JENDL-4.0:a new library for nuclear science and engineering.J.Nucl.Sci.Technol.48,1-30(2011).https://doi.org/10.1080/18811248.2011.9711675
17.D.L.Aldama,A.L.Nichols.ADS-2.0 A Test Library for Accelerators Driven Systems and New Reactor Design,International Atomic Energy Agency/Nuclear Data Section,INDC(NDS)-0545(2008)
18.A.C.Kahler,The NJOY Nuclear Data Processing System,Version 2016(Los Alamos National Security,Los Alamos,2016)
19.D.B.Pelowitz,MCNPX User’s Manual,Version 2.7.0(Los Alamos National Laboratory,Los Alamos,2011)
20.J.B.Blair,A.T.Michaelat,R.Yolanda et al.,International Handbook of Evaluated Criticality Safety Benchmark Experiments,NEA/NSC/DOC(95)03(2006)
21.M.B.Chadwick,P.Oblozinsky,M.Herman et al.,ENDF/B-VII.0:next generation evaluated nuclear data library for nuclear science and technology.Nucl.Data.Sheets 107,2931-3060(2006).https://doi.org/10.1016/j.nds.2006.11.001
22.S.C.Frankle,A Suite of Criticality Benchmarks for Validating Nuclear Data.Los Alamos National Laboratory,LA-13594(1999)
23.S.Hong,Y.W.Yang,L.Zhang et al.,Fabrication and validation of multigroup cross section library based on the OpenMC code.Nucl.Tech.40,43-48(2017).https://doi.org/10.11889/j.0253-3219.2017.hjs.40.040502