熔盐实验堆核数据引起反应性参数不确定度分析
|
摘要
反应堆设计中需给出各个参数不确定度,核数据是反应性相关参数不确定度的重要来源。利用SCALE6.1程序中TRITON(Transport Rigor Implemented with Time-dependent Operation for Neutronic depletion)、TSUNAMI-3D(Tools for Sensitivity and Uncertainty Analysis Methodology Implementation in Three Dimensions)和TSAR(Tool for Sensitivity Analysis of Reactivity Responses)模块,结合自带44群协方差数据库,分析了熔盐实验堆反应性相关参数。给出核数据不确定度导致寿期初和寿期末k_(eff)、控制棒价值及温度反应性不确定度分别为522×10~(-5)、506×10~(-5)、96.70×10~(-5)和8.90×10~(-5)。结合灵敏度系数和核数据的标准偏差分析,结果显示:对k_(eff)影响较大的核素及反应道为235U()、(n,γ)、~(238)U(n,γ)、C-graphite(n,el)、~7Li(n,γ)、~(239)Pu()、(n,f)和~(135)Xe(n,γ)等核反应数据;对控制棒价值和温度反应性影响比较大的核素及反应道为~(19)F(n,el)、~(58)Ni(n,γ)、~6Li(n,t)等核反应数据。
[Background] Uncertainty analysis is an essential and mandatory work for reactor design. Nuclear data is an important origin of uncertainty in reactivity parameters. [Purpose] This study aims to obtain and analyze the uncertainty of reactivity parameters and the more significant nuclear data of molten salt experiment reactor.[Methods] The transport rigor implemented with time-dependent operation for neutronic depletion(TRITON), tools for sensitivity and uncertainty analysis methodology implementation in three dimensions(TSUNAMI-3D) and tool for sensitivity analysis of reactivity responses(TSAR) modules of SCALE code are combined with its 44-group covariance data library to analyze the uncertainties of keffat the beginning of life(BOL) and the end of life(EOL),control rod worth(CRW) and temperature coefficients(TC) for molten salt experiment reactor, etc. [Results] The uncertainties are 522 × 10~(-5) and 506 × 10~(-5) for keffat BOL and EOL, and 96.70 × 10~(-5), 8.90 × 10~(-5) for CRW and TC respectively. [Conclusion] The analysis for sensitivity coefficients and covariation data shows that the reaction data of ~(235)U(),(n, γ),~(238)U(n, γ), C-graphite(n, el),~7Li(n, γ),~(239)Pu(),(n, f) and ~(135)Xe(n, γ) are more significant for keff uncertainty, and ~(19)F(n,el),~(58)Ni(n,γ),~6Li(n,t) are important for uncertainties of CRW and TC.
[Background] Uncertainty analysis is an essential and mandatory work for reactor design. Nuclear data is an important origin of uncertainty in reactivity parameters. [Purpose] This study aims to obtain and analyze the uncertainty of reactivity parameters and the more significant nuclear data of molten salt experiment reactor.[Methods] The transport rigor implemented with time-dependent operation for neutronic depletion(TRITON), tools for sensitivity and uncertainty analysis methodology implementation in three dimensions(TSUNAMI-3D) and tool for sensitivity analysis of reactivity responses(TSAR) modules of SCALE code are combined with its 44-group covariance data library to analyze the uncertainties of keffat the beginning of life(BOL) and the end of life(EOL),control rod worth(CRW) and temperature coefficients(TC) for molten salt experiment reactor, etc. [Results] The uncertainties are 522 × 10~(-5) and 506 × 10~(-5) for keffat BOL and EOL, and 96.70 × 10~(-5), 8.90 × 10~(-5) for CRW and TC respectively. [Conclusion] The analysis for sensitivity coefficients and covariation data shows that the reaction data of ~(235)U(),(n, γ),~(238)U(n, γ), C-graphite(n, el),~7Li(n, γ),~(239)Pu(),(n, f) and ~(135)Xe(n, γ) are more significant for keff uncertainty, and ~(19)F(n,el),~(58)Ni(n,γ),~6Li(n,t) are important for uncertainties of CRW and TC.
引文
1 US Department of Energy.A technology roadmap for generation IV nuclear energy systems[R].USA:Nuclear Energy Research Advisory Committee and the Generation IV International Forum,2002:GIF-002-00.
2 Heuer D,Merle-lucotte E,Brission R,et al.Possible configurations for the thorium molten salt reactor and advantages of the fast non-moderated version[J].Nuclear Science and Engineering,2009,161(1):78-89.DOI:10.13182/NSE07-49.
3 Zou C Y,Cai X Z,Jiang D Z,et al.Optimization of temperature coefficient and breeding ratio for a graphitemoderated molten salt reactor[J].Nuclear Engineering and Design,2015,281:114-120.DOI:10.1016/j.nucengdes.2014.11.022.
4 Yu C G,Li X X,Cai X Z,et al.Minor actinide incineration and Th-U breeding in a small FLiNaK1-7molten salt fast reactor[J].Annals of Nuclear Energy,2017,99:335-344.DOI:10.1016/j.anucene.2016.09.025.
5 Li X X,Cai X Z,Jiang D Z,et al.Analysis of thorium and uranium based nuclear fuel options in fluoride saltcooled high-temperature reactor[J].Progress in Nuclear Energy,2015,78:285-290.DOI:10.1016/j.pnucene.2014.10.004.
6李广超,邹杨,余成刚,等.基于熔盐快堆的模型优化与Th-U增殖性能研究[J].核技术,2017,40(2):020603.DOI:10.11889/j.0253-3219.2017.hjs.40.020603.LI Guangchao,ZOU Yang,YU Chenggang,et al.Model optimization and analysis of Th-U breeding based on MSFR[J].Nuclear Techniques,2017,40(2):020603.DOI:10.11889/j.0253-3219.2017.hjs.40.020603.
7郭晨,冀瑞敏,陈金根,等.钍基液态燃料熔盐实验堆氙毒分析[J].核技术,2017,40(4):040602.DOI:10.11889/j.0253-3219.2017.hjs.40.040602.GUO Chen,JI Ruimin,CHEN Jingen,et al.Xenon analysis of thorium molten salt experiment reactor-liquid fuel[J].Nuclear Techniques,2017,40(4):040602.DOI:10.11889/j.0253-3219.2017.hjs.40.040602.
8江绵恒,徐洪杰,戴志敏.未来先进核裂变能--TMSR核能系统[J].中国科学院院刊,2012,27(3):366-374.DOI:10.3969/j.issn.1000-3045.2012.03.016.JIANG Mianheng,XU Hongjie,DAI Zhimin.Advanced nuclear fission energy-TMSR nuclear energy systems[J].Bulletin of Chinese Academy of Sciences,2012,27(3):366-374.DOI:10.3969/j.issn.1000-3045.2012.03.016.
9何杰,夏晓斌,蔡军,等.2 MW液态钍基熔盐实验堆主屏蔽温度场分析[J].核技术,2016,39(4):040601.DOI:10.11889/j.0253-3219.2016.hjs.39.040601.HE Jie,XIA Xiaobin,CAI Jun,et al.Temperature field analysis for the main shielding of the 2-MW thoriumbased molten salt experimental reactor[J].Nuclear Techniques,2016,39(4):040601.DOI:10.11889/j.0253-3219.2016.hjs.39.040601.
10魏波,张正军,童楚楚,等.中子入射砷核同位素反应全套微观数据的计算与分析[J].核技术,2018,41(7):070502.DOI:10.11889/j.0253-3219.2018.hjs.41.070502.WEI Bo,ZHANG Zhengjun,TONG Chuchu,et al.Theoretical calculations and analysis of the full set of microcosmic data for n+74,75,77,79As nuclear reaction[J].Nuclear Techniques,2018,41(7):070502.DOI:10.11889/j.0253-3219.2018.hjs.41.070502.
11 Ivanov K,Avramova M,Kamerow S.Overview and discussion of phase I of the OECD LWR UAMbenchmark activity[C].International Conference on Mathematics,Computational Methods Reactor Physics03060(MC2009),2009.
12 Weisbin C R,Oblow E M,Marable J H,et al.Application of sensitivity and uncertainty methodology to fast reactor integral experiment analysis[J].Nuclear Science and Engineering,1978,66(3):307-333.DOI:10.13182/NSE78-3.
13 Rimpaultg G,Plisson D,Tommasi J,et al.The ERANOScode and data system for fast reactor neutronics analyses[C].Proceedings of PHYSOR 2002 Conference,USA:American Nuclear Society,2002.
14 Kodeli I.Multidimensional deterministic nuclear data sensitivity and uncertainty code system,method and application[J].Nuclear Science and Engineering,2001,138(1):45-66.DOI:10.13182/NSE00-43.
15 Scale:a comprehensive modeling and simulation suite for nuclear safety analysis and design[R].USA:Oak Ridge National Laboratory,2011.
16 Sugawara T,Sarotto M,Stankovskiy A,et al.Nuclear data sensitivity-uncertainty analysis for XT-ADS[J].Annals of Nuclear Energy,2011,38:1098-1108.DOI:10.1016/j.anucene.2010.12.018.
17 Iwamoto H,Nishihara K,Sugawara T,et al.Sensitivity and uncertainty analysis for an accelerator-driven system with JENDL-4.0[J].Journal of Nuclear Science and Technology,2013,50(8):856-862.DOI:10.1080/00223131.2013.811954.
18 Alhassan E,Sj?strand H,Helgesson P,et al.Uncertainty and correlation analysis of lead nuclear data on reactor parameters for the European lead cooled training reactor[J].Annals of Nuclear Energy,2015,75:26-37.DOI:10.1016/j.anucene.2014.07.043.
19 Elam K R,Rearden B T.Use of sensitivity and uncertainty analysis to select benchmark experiments for the validation of computer codes and data[J].Nuclear Science and Engineering 2003,145:196-212.DOI:10.13182/NSE03-A2376.
20胡泽华,王佳,孙伟力,等.基准模型keff对核数据的灵敏度分析及其不确定度量化[J].原子能科学技术,2013,47(增):312-317.DOI:10.7538/yzk.2013.47.S0.0312.HU Zehua,WANG Jia,SUN Weili,et al.Sensitivity and uncertainty analysis of calculated keffon benchmark models due to uncertainties of nuclear data[J].Atomic Energy Science and Technology,2013,47(Suppl):312-317.DOI:10.7538/yzk.2.13.47.S0.0312.
21万承辉,曹良志,吴宏春,等.基于抽样方法的特征值不确定度分析[J].原子能科学技术,2015,49(11):1954-1960.DOI:10.7538/yzk.2015.49.11.1954.WAN Chenghui,CAO Liangzhi,WU Hongchun,et al.Eigenvalue uncertainty analysis based on statistical sampling method[J].Atomic Energy Science and Technology,2015,49(11):1954-1960.DOI:10.7538/yzk.2015.49.11.1954.
22杨群,邹杨,于世和,等.熔盐冷却球床堆核数据不确定性对k∞的影响[J].原子能科学技术,2013,47(增):678-682.DOI:10.7538/yzk.2013.47.S1.0678.YANG Qun,ZOU Yang,YU Shihe,et al.Effect of nuclear data uncertainty on k∞in molten salt cooled pebble bed reactor[J].Atomic Energy Science and Technology,2013,47(Suppl):678-682.DOI:10.7538/yzk.2013.47.S1.0678.
23杨军,喻宏,徐李,等.中国实验快堆keff计算值对核数据的灵敏度和不确定度分析[J].核动力,2015,35(S2):71-75.DOI:10.13832/j.jnpe.2014.S2.0071.YANG Jun,YU Hong,XU Li,et al.Analysis of sensitivity and uncertainty of calculated keffto nuclear data on China experimental fast reactor[J].Nuclear Power Engineering,2015,35(S2):71-75.DOI:10.13832/j.jnpe.2014.S2.0071.
24潘昕怿,兰兵,韩向臻,等.基于随机抽样法的多群核数据不确定性影响分析[J].强激光与粒子束,2017,29(4):046005.DOI:10.11884/HPLPB201729.160273.PAN Xinyi,LAN Bing,HAN Xiangzhen,et al.Analysis on influence of multigroup nuclear data uncertainty based on stochastic sampling method[J].High Power Laser and Particle Beams,2017,29(4):046005.DOI:10.11884/HPLPB201729.160273.
25王立鹏,张信一,郭和伟,等.核截面不确定度对西安脉冲堆keff计算结果的影响分析[J].现代应用物理,2016,7(4):3-8.DOI:10.3969/j.issn.2095-6223.2016.04.001.WANG Lipeng,ZHANG Xinyi,GUO Hewei,et al.Analysis on the effect of nuclear cross section data uncertainty to keffcalculation in Xi'an pulsed reactor[J].Modern Applied Physics,2016,7(4):3-8.DOI:10.3969/j.issn.2095-6223.2016.04.001.
26胡泽华,叶涛,刘雄国,等.抽样法与灵敏度法keff不确定度量化[J].物理学报,2017,66(1):57-65.DOI:10.7498/aps.66.012801.HU Zehua,YE Tao,LIU Xiongguo,et al.Uncertainty quantification in the calculation of keffusing sensitity and stochastic sampling method[J].Acta Physics Sinces,2017,66(1):57-65.DOI:10.7498/aps.66.012801.
27刘亚芬,郭锐,胡继峰,等.熔盐实验堆中燃料核素的灵敏度系数计算分析[J].原子能科学技术,2013,47(增):270-274.DOI:10.7538/yzk.2013.47.S0.0270.LIU Yafen,GUO Rui,HU Jifeng,et al.Sensitivity coefficient analysis of fuel nuclides on molten salt reactor experiment[J].Atomic Energy Science and Technology,2013,47(Suppl):270-274.DOI:10.7538/yzk.2013.47.S0.0270.
28 Zu T,Yang C,Cao L,et al.Nuclear data uncertainty propagation analysis for depletion calculation in PWRand FR pin-cells[J].Annals of Nuclear Energy,2016,94:399-408.DOI:10.1016/j.anucene.2016.04.006.
29胡继峰,余呈刚,邹春燕,等.钍增殖熔盐堆不同燃耗核数据不确定度分析[J].原子能科学技术,2017,51(11):2013-2020.DOI:10.7538/yzk.2017.51.11.2013.HU Jifeng,YU Chenggang,ZOU Chunyan,et al.Analysis of uncertainty of keffto nuclear data in thorium molten salt breeder reactor with burnup[J].Atomic Energy Science and Technology,2017,51(11):2013-2020..DOI:10.7538/yzk.2017.51.11.2013.
30 Ronertson R C.MSRE design and operations report,part I:description of reactor design[R].ORNL-TM-728,Tennessee,America:ORNL,1965.DOI:10.2172/4654707.
2 Heuer D,Merle-lucotte E,Brission R,et al.Possible configurations for the thorium molten salt reactor and advantages of the fast non-moderated version[J].Nuclear Science and Engineering,2009,161(1):78-89.DOI:10.13182/NSE07-49.
3 Zou C Y,Cai X Z,Jiang D Z,et al.Optimization of temperature coefficient and breeding ratio for a graphitemoderated molten salt reactor[J].Nuclear Engineering and Design,2015,281:114-120.DOI:10.1016/j.nucengdes.2014.11.022.
4 Yu C G,Li X X,Cai X Z,et al.Minor actinide incineration and Th-U breeding in a small FLiNaK1-7molten salt fast reactor[J].Annals of Nuclear Energy,2017,99:335-344.DOI:10.1016/j.anucene.2016.09.025.
5 Li X X,Cai X Z,Jiang D Z,et al.Analysis of thorium and uranium based nuclear fuel options in fluoride saltcooled high-temperature reactor[J].Progress in Nuclear Energy,2015,78:285-290.DOI:10.1016/j.pnucene.2014.10.004.
6李广超,邹杨,余成刚,等.基于熔盐快堆的模型优化与Th-U增殖性能研究[J].核技术,2017,40(2):020603.DOI:10.11889/j.0253-3219.2017.hjs.40.020603.LI Guangchao,ZOU Yang,YU Chenggang,et al.Model optimization and analysis of Th-U breeding based on MSFR[J].Nuclear Techniques,2017,40(2):020603.DOI:10.11889/j.0253-3219.2017.hjs.40.020603.
7郭晨,冀瑞敏,陈金根,等.钍基液态燃料熔盐实验堆氙毒分析[J].核技术,2017,40(4):040602.DOI:10.11889/j.0253-3219.2017.hjs.40.040602.GUO Chen,JI Ruimin,CHEN Jingen,et al.Xenon analysis of thorium molten salt experiment reactor-liquid fuel[J].Nuclear Techniques,2017,40(4):040602.DOI:10.11889/j.0253-3219.2017.hjs.40.040602.
8江绵恒,徐洪杰,戴志敏.未来先进核裂变能--TMSR核能系统[J].中国科学院院刊,2012,27(3):366-374.DOI:10.3969/j.issn.1000-3045.2012.03.016.JIANG Mianheng,XU Hongjie,DAI Zhimin.Advanced nuclear fission energy-TMSR nuclear energy systems[J].Bulletin of Chinese Academy of Sciences,2012,27(3):366-374.DOI:10.3969/j.issn.1000-3045.2012.03.016.
9何杰,夏晓斌,蔡军,等.2 MW液态钍基熔盐实验堆主屏蔽温度场分析[J].核技术,2016,39(4):040601.DOI:10.11889/j.0253-3219.2016.hjs.39.040601.HE Jie,XIA Xiaobin,CAI Jun,et al.Temperature field analysis for the main shielding of the 2-MW thoriumbased molten salt experimental reactor[J].Nuclear Techniques,2016,39(4):040601.DOI:10.11889/j.0253-3219.2016.hjs.39.040601.
10魏波,张正军,童楚楚,等.中子入射砷核同位素反应全套微观数据的计算与分析[J].核技术,2018,41(7):070502.DOI:10.11889/j.0253-3219.2018.hjs.41.070502.WEI Bo,ZHANG Zhengjun,TONG Chuchu,et al.Theoretical calculations and analysis of the full set of microcosmic data for n+74,75,77,79As nuclear reaction[J].Nuclear Techniques,2018,41(7):070502.DOI:10.11889/j.0253-3219.2018.hjs.41.070502.
11 Ivanov K,Avramova M,Kamerow S.Overview and discussion of phase I of the OECD LWR UAMbenchmark activity[C].International Conference on Mathematics,Computational Methods Reactor Physics03060(MC2009),2009.
12 Weisbin C R,Oblow E M,Marable J H,et al.Application of sensitivity and uncertainty methodology to fast reactor integral experiment analysis[J].Nuclear Science and Engineering,1978,66(3):307-333.DOI:10.13182/NSE78-3.
13 Rimpaultg G,Plisson D,Tommasi J,et al.The ERANOScode and data system for fast reactor neutronics analyses[C].Proceedings of PHYSOR 2002 Conference,USA:American Nuclear Society,2002.
14 Kodeli I.Multidimensional deterministic nuclear data sensitivity and uncertainty code system,method and application[J].Nuclear Science and Engineering,2001,138(1):45-66.DOI:10.13182/NSE00-43.
15 Scale:a comprehensive modeling and simulation suite for nuclear safety analysis and design[R].USA:Oak Ridge National Laboratory,2011.
16 Sugawara T,Sarotto M,Stankovskiy A,et al.Nuclear data sensitivity-uncertainty analysis for XT-ADS[J].Annals of Nuclear Energy,2011,38:1098-1108.DOI:10.1016/j.anucene.2010.12.018.
17 Iwamoto H,Nishihara K,Sugawara T,et al.Sensitivity and uncertainty analysis for an accelerator-driven system with JENDL-4.0[J].Journal of Nuclear Science and Technology,2013,50(8):856-862.DOI:10.1080/00223131.2013.811954.
18 Alhassan E,Sj?strand H,Helgesson P,et al.Uncertainty and correlation analysis of lead nuclear data on reactor parameters for the European lead cooled training reactor[J].Annals of Nuclear Energy,2015,75:26-37.DOI:10.1016/j.anucene.2014.07.043.
19 Elam K R,Rearden B T.Use of sensitivity and uncertainty analysis to select benchmark experiments for the validation of computer codes and data[J].Nuclear Science and Engineering 2003,145:196-212.DOI:10.13182/NSE03-A2376.
20胡泽华,王佳,孙伟力,等.基准模型keff对核数据的灵敏度分析及其不确定度量化[J].原子能科学技术,2013,47(增):312-317.DOI:10.7538/yzk.2013.47.S0.0312.HU Zehua,WANG Jia,SUN Weili,et al.Sensitivity and uncertainty analysis of calculated keffon benchmark models due to uncertainties of nuclear data[J].Atomic Energy Science and Technology,2013,47(Suppl):312-317.DOI:10.7538/yzk.2.13.47.S0.0312.
21万承辉,曹良志,吴宏春,等.基于抽样方法的特征值不确定度分析[J].原子能科学技术,2015,49(11):1954-1960.DOI:10.7538/yzk.2015.49.11.1954.WAN Chenghui,CAO Liangzhi,WU Hongchun,et al.Eigenvalue uncertainty analysis based on statistical sampling method[J].Atomic Energy Science and Technology,2015,49(11):1954-1960.DOI:10.7538/yzk.2015.49.11.1954.
22杨群,邹杨,于世和,等.熔盐冷却球床堆核数据不确定性对k∞的影响[J].原子能科学技术,2013,47(增):678-682.DOI:10.7538/yzk.2013.47.S1.0678.YANG Qun,ZOU Yang,YU Shihe,et al.Effect of nuclear data uncertainty on k∞in molten salt cooled pebble bed reactor[J].Atomic Energy Science and Technology,2013,47(Suppl):678-682.DOI:10.7538/yzk.2013.47.S1.0678.
23杨军,喻宏,徐李,等.中国实验快堆keff计算值对核数据的灵敏度和不确定度分析[J].核动力,2015,35(S2):71-75.DOI:10.13832/j.jnpe.2014.S2.0071.YANG Jun,YU Hong,XU Li,et al.Analysis of sensitivity and uncertainty of calculated keffto nuclear data on China experimental fast reactor[J].Nuclear Power Engineering,2015,35(S2):71-75.DOI:10.13832/j.jnpe.2014.S2.0071.
24潘昕怿,兰兵,韩向臻,等.基于随机抽样法的多群核数据不确定性影响分析[J].强激光与粒子束,2017,29(4):046005.DOI:10.11884/HPLPB201729.160273.PAN Xinyi,LAN Bing,HAN Xiangzhen,et al.Analysis on influence of multigroup nuclear data uncertainty based on stochastic sampling method[J].High Power Laser and Particle Beams,2017,29(4):046005.DOI:10.11884/HPLPB201729.160273.
25王立鹏,张信一,郭和伟,等.核截面不确定度对西安脉冲堆keff计算结果的影响分析[J].现代应用物理,2016,7(4):3-8.DOI:10.3969/j.issn.2095-6223.2016.04.001.WANG Lipeng,ZHANG Xinyi,GUO Hewei,et al.Analysis on the effect of nuclear cross section data uncertainty to keffcalculation in Xi'an pulsed reactor[J].Modern Applied Physics,2016,7(4):3-8.DOI:10.3969/j.issn.2095-6223.2016.04.001.
26胡泽华,叶涛,刘雄国,等.抽样法与灵敏度法keff不确定度量化[J].物理学报,2017,66(1):57-65.DOI:10.7498/aps.66.012801.HU Zehua,YE Tao,LIU Xiongguo,et al.Uncertainty quantification in the calculation of keffusing sensitity and stochastic sampling method[J].Acta Physics Sinces,2017,66(1):57-65.DOI:10.7498/aps.66.012801.
27刘亚芬,郭锐,胡继峰,等.熔盐实验堆中燃料核素的灵敏度系数计算分析[J].原子能科学技术,2013,47(增):270-274.DOI:10.7538/yzk.2013.47.S0.0270.LIU Yafen,GUO Rui,HU Jifeng,et al.Sensitivity coefficient analysis of fuel nuclides on molten salt reactor experiment[J].Atomic Energy Science and Technology,2013,47(Suppl):270-274.DOI:10.7538/yzk.2013.47.S0.0270.
28 Zu T,Yang C,Cao L,et al.Nuclear data uncertainty propagation analysis for depletion calculation in PWRand FR pin-cells[J].Annals of Nuclear Energy,2016,94:399-408.DOI:10.1016/j.anucene.2016.04.006.
29胡继峰,余呈刚,邹春燕,等.钍增殖熔盐堆不同燃耗核数据不确定度分析[J].原子能科学技术,2017,51(11):2013-2020.DOI:10.7538/yzk.2017.51.11.2013.HU Jifeng,YU Chenggang,ZOU Chunyan,et al.Analysis of uncertainty of keffto nuclear data in thorium molten salt breeder reactor with burnup[J].Atomic Energy Science and Technology,2017,51(11):2013-2020..DOI:10.7538/yzk.2017.51.11.2013.
30 Ronertson R C.MSRE design and operations report,part I:description of reactor design[R].ORNL-TM-728,Tennessee,America:ORNL,1965.DOI:10.2172/4654707.
© 2004-2018 中国地质图书馆版权所有 京ICP备05064691号 京公网安备11010802017129号 地址：北京市海淀区学院路29号 邮编：100083 电话：办公室：(+86 10)66554848；文献借阅、咨询服务、科技查新：66554700 |