聚变堆水冷回路中多物相活化腐蚀产物计算分析
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摘要
聚变堆水冷回路中结构材料与冷却剂接触后产生的腐蚀产物随冷却剂流经堆芯辐照区时,极易被中子活化,活化后的腐蚀产物形成一个辐射场,在反应堆维护及检修过程中会对工作人员产生较大的职业照射剂量。在活化腐蚀产物源项分析程序CATE V2.1的基础上,对计算模型进行改进,开发出基于四物相三节点模型的活化腐蚀产物源项分析程序CATE V3.0,全面考虑了活化腐蚀产物的多种物质形态(氧化层、沉积层、离子、颗粒)在水冷回路中的主要行为,从而可以更加准确地评估活化腐蚀产物导致的迁移源项。使用活化腐蚀产物源项程序CATE V3.0对国际热核聚变实验堆(International Thermonuclear Experimental Reactor,ITER)的偏滤器水冷回路进行建模仿真,计算得到了活化腐蚀产物的成分和放射性活度在偏滤器水冷回路中的分布以及随时间的变化规律,并将CATE V3.0模拟得到的放射性活度通过点核积分程序计算出反应堆正常运行1.2 a的剂量率。结果表明:辐照区的放射性活度主要来自氧化层,非辐照区的放射性活度主要来自沉积层;在反应堆运行期间,放射性活度主要来自短寿命核素64Cu和60Com,但剂量率主要来自长寿命核素58Co和60Co;停堆后,短寿命核素会迅速衰变消失,长寿命核素成为水冷回路中的放射性活度和剂量率主要贡献者。
[Background] In the water-cooled loops of fusion reactor, corrosion products are produced in the process of interaction between the structure materials and the coolant. When coolant flows in the flux region, the corrosion products will be activated by neutrons to produce activated corrosion products(ACPs). The radiation field generated by the ACPs has the greatest impact on the occupational radiation exposure(ORE) of personnel in the process of maintenance and overhaul. [Purpose] This study aims to accurately analyze the source terms of ACPs in water-cooled loops of fusion reactor, and perform some simulation calculation of ACPs. [Methods] Firstly a fourphase three-node model for calculating radioactivity of ACPs was proposed, in which the main behaviors of ions,particles, deposits layer and oxide layer were considered, and the code CATE V3.0 was developed based on CATE V2.1. Then the composition and radioactivity of ACPs in the divertor cooling loop of International Thermonuclear Experimental Reactor(ITER) were calculated with CATE V3.0. Finally the dose rate at shutdown after normally operation for 1.2 a was calculated with the point kernel code ARShield. [Results & Conclusions] The oxide layer is the main contributor to radioactivity in the flux region whilst deposits layer is the main contributor in the out-flux region. The short-lived nuclides such as64 Cu and60 Com, are the main contributors of radioactivity during the operation of reactor, but long-lived nuclides such as58 Co and60 Co, are the main contributors to the dose rate due to the decay of the short-lived nuclides after shutdown of reactor.
[Background] In the water-cooled loops of fusion reactor, corrosion products are produced in the process of interaction between the structure materials and the coolant. When coolant flows in the flux region, the corrosion products will be activated by neutrons to produce activated corrosion products(ACPs). The radiation field generated by the ACPs has the greatest impact on the occupational radiation exposure(ORE) of personnel in the process of maintenance and overhaul. [Purpose] This study aims to accurately analyze the source terms of ACPs in water-cooled loops of fusion reactor, and perform some simulation calculation of ACPs. [Methods] Firstly a fourphase three-node model for calculating radioactivity of ACPs was proposed, in which the main behaviors of ions,particles, deposits layer and oxide layer were considered, and the code CATE V3.0 was developed based on CATE V2.1. Then the composition and radioactivity of ACPs in the divertor cooling loop of International Thermonuclear Experimental Reactor(ITER) were calculated with CATE V3.0. Finally the dose rate at shutdown after normally operation for 1.2 a was calculated with the point kernel code ARShield. [Results & Conclusions] The oxide layer is the main contributor to radioactivity in the flux region whilst deposits layer is the main contributor in the out-flux region. The short-lived nuclides such as64 Cu and60 Com, are the main contributors of radioactivity during the operation of reactor, but long-lived nuclides such as58 Co and60 Co, are the main contributors to the dose rate due to the decay of the short-lived nuclides after shutdown of reactor.
引文
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9 Li L,Zhang J Y,Guo Q Y,et al.Evaluation of ACPs in China fusion engineering test reactor using CATE 2.1code[J].Science and Technology of Nuclear Installations,2017:2936069.DOI:10.1155/2017/2936069.
10 Lister D H,McAlpine E,Hocking W H.Corrosionproduct release in light water reactors[R].US:Electric Power Research Institute(EPRI),NP-3460,2008.
11 ITER-JCT I.Generic site safety report GSSR volume III-radiological and energy source terms(G 84 RI 3 R0.2)[R].ITER-JCT,2004.
12 Karditsas P J,Alib S M,Wan D.Copper corrosion and activation in water cooling loops under fusion irradiation conditions[J].Journal of Nuclear Materials,2000,283?287:1346?1350.DOI:10.1016/S0022-3115(00)00122-7.
13 Li L,Zhang J Y,He S X,et al.The development of twophase three-node model used to simulate the transport of ACPs[J].Progress in Nuclear Energy,2017,97:99?105.DOI:10.1016/j.pnucene.2016.12.015.
14 Forrest R A,Kopecky J,Sublet J C.The European activation file:EAF-2007 neutron-induced cross section library[M].EURATOM/UKAEA Fusion Association,2007.
15 Forrest R A.The European activation file:EAF-2007decay data library[M].EURATOM/UKAEA Fusion Association,2007.
16 He S X,Zang Q Y,Zhang J Y.Development and validation of an interactive efficient dose rates distribution calculation program arshield for visualization of radiation field in nuclear power plants[J].Radiation Protection Dosimetry,2016,174(2):159?166.DOI:10.1093/rpd/ncw127.
2 Rafique M,Mirza N M,Mirza S M,et al.Review of computer codes for modeling corrosion product transport and activity build-up in light water reactors[J].Nukleonika,2010,55(3):263?269.
3 Kang S,Sejvar J.CORA-II model of PWR corrosionproduct transport[R].Westinghouse Electric Corporation,Pittsburgh,PA,USA,1985.
4 Beslu P,Robin J C,Coulet F,et al.PACTOLE:a computer code to predict the activation and transport of corrosion products in PWRs[R].CEA Centre d'Etudes de Cadarache,1994.
5 Di Pace L,Dacquait F,Schindler P,et al.Development of the PACTITER code and its application to safety analyses of ITER primary cooling water system[J].Fusion Engineering and Design,2007,82(3):237?247.DOI:10.1016/j.fusengdes.2006.11.002.
6 Lee C B.Modeling of corrosion product transport in PWR primary coolant[D].Cambridge,Massachusetts US:Massachusetts Institute of Technology,1990.
7 Karditsas P J.Activation product transport using TRACT:ORE estimation of an ITER cooling loop[J].Fusion Engineering and Design,1999,45(2):169?185.DOI:10.1016/S0920-3796(99)00004-6.
8李璐,张竞宇,郭庆洋,等.水冷聚变堆主回路活化产物源项计算分析[J].核技术,2016,39(11):110603.DOI:1011889/j.0253-3219.2016.hjs.39.110603.LI Lu,ZHANG Jingyu,GUO Qingyang,et al.Calculation and analysis of activation products source term in water-cooled fusion reactor primary circuit[J].Nuclear Techniques,2016,39(11):110603.DOI:10.11889/j.0253-3219.2016.hjs.39.110603.
9 Li L,Zhang J Y,Guo Q Y,et al.Evaluation of ACPs in China fusion engineering test reactor using CATE 2.1code[J].Science and Technology of Nuclear Installations,2017:2936069.DOI:10.1155/2017/2936069.
10 Lister D H,McAlpine E,Hocking W H.Corrosionproduct release in light water reactors[R].US:Electric Power Research Institute(EPRI),NP-3460,2008.
11 ITER-JCT I.Generic site safety report GSSR volume III-radiological and energy source terms(G 84 RI 3 R0.2)[R].ITER-JCT,2004.
12 Karditsas P J,Alib S M,Wan D.Copper corrosion and activation in water cooling loops under fusion irradiation conditions[J].Journal of Nuclear Materials,2000,283?287:1346?1350.DOI:10.1016/S0022-3115(00)00122-7.
13 Li L,Zhang J Y,He S X,et al.The development of twophase three-node model used to simulate the transport of ACPs[J].Progress in Nuclear Energy,2017,97:99?105.DOI:10.1016/j.pnucene.2016.12.015.
14 Forrest R A,Kopecky J,Sublet J C.The European activation file:EAF-2007 neutron-induced cross section library[M].EURATOM/UKAEA Fusion Association,2007.
15 Forrest R A.The European activation file:EAF-2007decay data library[M].EURATOM/UKAEA Fusion Association,2007.
16 He S X,Zang Q Y,Zhang J Y.Development and validation of an interactive efficient dose rates distribution calculation program arshield for visualization of radiation field in nuclear power plants[J].Radiation Protection Dosimetry,2016,174(2):159?166.DOI:10.1093/rpd/ncw127.