强流氘氚聚变中子源HINEG设计研究
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摘要
强流氘氚聚变中子源HINEG(High Intensity D-T Fusion Neutron Generator)研发分两期:HINEG-Ⅰ为直流脉冲双模式,已成功产生中子强度1.1×10~(12)n/s的氘氚聚变中子,并实现连续稳定运行;HINEG-Ⅱ中子强度设计指标为10~(14)~10~(15)n/s量级,重点突破强流离子源和高载热氚靶技术。HNEG中子源可开展中子学方法程序与核数据、辐射屏蔽与防护、材料活化与辐照损伤机理和部件中子学性能等核能与核安全研究,同时也可在核医学与放射治疗、中子照相等领域拓展核技术应用研究。本文简要介绍HINEG总体设计方案与关键技术研究进展。
The R&D of HINEG(High Intensity D-T Fusion Neutron Generator)includes two phases:HINEG-Ⅰ and HINEG-Ⅱ.HINEG-Ⅰ is designed to generate both the steady beam and pulsed beam,and have successfully produced a D-T fusion neutron yield of up to 1.l×10~(12)n/s.HINEG-Ⅱ aims at a high neutron yield of 10~(14)~10~(15)n/s neutrons via high speed rotating tritium target system and high intensity ion source.HINEG can be used for research of nuclear technology and safety including the validation of neutronics method and software,radiation shielding and protection,mechanism of materials activation and radiation damage as well as neutronics performance of components.Its application can also be extended to nuclear medicine,radiotherapy,neutron imaging and other nuclear technology applications.This paper introduces the scenario of design and progress in R&D of key technology of HINEG.
The R&D of HINEG(High Intensity D-T Fusion Neutron Generator)includes two phases:HINEG-Ⅰ and HINEG-Ⅱ.HINEG-Ⅰ is designed to generate both the steady beam and pulsed beam,and have successfully produced a D-T fusion neutron yield of up to 1.l×10~(12)n/s.HINEG-Ⅱ aims at a high neutron yield of 10~(14)~10~(15)n/s neutrons via high speed rotating tritium target system and high intensity ion source.HINEG can be used for research of nuclear technology and safety including the validation of neutronics method and software,radiation shielding and protection,mechanism of materials activation and radiation damage as well as neutronics performance of components.Its application can also be extended to nuclear medicine,radiotherapy,neutron imaging and other nuclear technology applications.This paper introduces the scenario of design and progress in R&D of key technology of HINEG.
引文
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[17]http://www-nds.iaea.org
[18]S.Unholzer,H.Freiesleben,H.Klein,and K.Seidel,The measurement of neutron and neutron induced photon spectra in fusion related assemblies[J],Nuclear Instrument and Methods in Physics Research A,160,2002,476.
[19]Q.Huang,FDS Team,Development status of CLAM steel for fusion application,J.Nucl Mater.455(2014)649-654.
[20]Wu Y C,FDS Team.Design Status and Development Strategy of China Liquid Lithium-lead Blankets and Related Material Technology[J].J.Nucl.Mater.,2007,367-370:1410-1415.
[21]Wu Y C,FDS Team.Design Analysis of the China Dual-functional Lithium Lead(DFLL)Test Blanket Module in ITER[J].Fusion Eng.Des.,2007,82:1893-1903.
[22]K.M.Feng,C.H.Pan,G.S.Zhang,et al.,Progress on design and R&D for helium-cooled ceramic breeder TBM in China,Fusion Eng.Des.,2012,87:1138-1145.
[2]H.Tanigawa,K.Shiba,A.Moeslang,R.E.Stoller,R.Lindau,M.A.Sokolov,G.R.Odette,R.J.Kurtz,and S.Jitsukawa.Status and key issues of reduced activation ferritic/martensitic steels as the structural material for a DEMO blanket.Journal of Nuclear Materials,417,9(2011).
[3]C.M.LOGAN and D.W.HEIKKINEN.RTNS-Ⅱ-A FUSION MATERIALS RESEARCH TOOL.Nuclear Instruments and Methods.105,200(1982).
[4]V.D.Kovalchuk,V.V.Mostovoy,V.I.Tereshkin,and D.V.Markovskij.Activation study at SNEG-13facility of the candidate ferritic steel 10X9VFA.Fusion Engineering and Design.343,42(1998).
[5]Kenji SUMITA.TRITIUM SOLID TARGETS FOR INTENSE D-T NEUTRON PRODUCTION AND THE RELATED PROBLEMS.Nuclear Instruments and Methods in Physics Research A.345,282(1989).
[6]M.Martone,M.Angelone,M.Pillon.The 14 MeV Frascati neutron generator.Journal of Nuclear Materials.1661,212(1994).
[7]沈冠仁,关遐令,陈洪涛.CPNG脉冲化装置的研制[J].核技术,730,25(2002).
[8]苏桐龄,强流中子发生器及其应用[J].核技术,553,12(1989).
[9]刘荣,亢武,周长庚.纳秒脉冲/直流强中子发生器及其性能测试[J].中国工程物理研究院科技年报,2009:39-39.
[10]Y.Wu,FDS Team,CAD-Based Interface Programs for Fusion Neutron Transport Simulation,Fusion Eng.Des.84(2009)1987-1992.
[11]Y.Wu,Z.Xie,U.Fischer,A Discrete Ordinates Nodal Method for One-Dimensional Neutron Transport Calculation in Curvilinear Geometries,Nucl.Sci.Eng.133(3)(1999)350-357.
[12]吴宜灿,李静惊,李莹,曾勤,陈明亮,郑善良,许德政,蒋洁琼,卢磊,丁爱平,胡海敏,龙鹏程,柏云清,罗月童,曹瑞芬,邹俊,何兆忠,黄群英,FDS团队.大型集成多功能中子学计算与分析系统VisualBUS的研究与发展[J].核科学与工程,2007,27(4):365-373.
[13]吴宜灿,胡丽琴,龙鹏程,罗月童,李亚洲,曾勤,卢磊,张俊军,邹俊,许德政,柏云清,周涛,陈红丽,彭蕾,宋勇,黄群英,FDS团队.先进核能系统设计分析软件与数据库研发进展[J].核科学与工程,2010,30(1):55-64.
[14]吴宜灿,俞盛朋,程梦云,宋婧,何桃,郝丽娟,胡丽琴,龙鹏程,罗月童,汪冬,甘俭,王文,吴斌,董良,杨琪.多物理耦合分析自动建模软件SuperMC/MCAM 5.2的设计与实现[J].原子能科学技术,2015,49:23-28.
[15]Y.Wu,J.Song,H.Zheng,et al.,CAD-Based Monte Carlo Program for Integrated Simulation of Nuclear System SuperMC.Ann.Nucl.Energy,2015,82:161-168.
[16]Jaime Marian,Yuan Hoang,Michael Fluss,Luke L.Hsiung,A review of helium-hydrogen synergistic effects in radiation damage observed in fusion energy steels and an interaction model to guide future understanding[J].Journal of Nuclear Materials,462(2015)409-421.
[17]http://www-nds.iaea.org
[18]S.Unholzer,H.Freiesleben,H.Klein,and K.Seidel,The measurement of neutron and neutron induced photon spectra in fusion related assemblies[J],Nuclear Instrument and Methods in Physics Research A,160,2002,476.
[19]Q.Huang,FDS Team,Development status of CLAM steel for fusion application,J.Nucl Mater.455(2014)649-654.
[20]Wu Y C,FDS Team.Design Status and Development Strategy of China Liquid Lithium-lead Blankets and Related Material Technology[J].J.Nucl.Mater.,2007,367-370:1410-1415.
[21]Wu Y C,FDS Team.Design Analysis of the China Dual-functional Lithium Lead(DFLL)Test Blanket Module in ITER[J].Fusion Eng.Des.,2007,82:1893-1903.
[22]K.M.Feng,C.H.Pan,G.S.Zhang,et al.,Progress on design and R&D for helium-cooled ceramic breeder TBM in China,Fusion Eng.Des.,2012,87:1138-1145.