本文選題：活化腐蝕產(chǎn)物　切入點：CATE程序　出處：《華北電力大學(北京)》2017年博士論文　論文類型：學位論文

【摘要】：放射性源項關(guān)系反應堆系統(tǒng)運行、維修維護及退役等環(huán)節(jié),對輻射防護、個人和集體劑量以及安全分析有重大影響。水冷反應堆中,結(jié)構(gòu)材料與冷卻劑接觸發(fā)生腐蝕,生成了較穩(wěn)定的氧化層,金屬離子穿過氧化層釋放進入冷卻劑。輻照區(qū)的氧化層以及由冷卻劑攜帶進入輻照區(qū)的金屬離子受中子輻照發(fā)生活化反應成為放射性物質(zhì),冷卻劑中的放射性物質(zhì)在冷卻劑的攜帶下沉積到非輻照區(qū)形成了γ輻射場,對電廠檢修維護及運行人員構(gòu)成輻照危害。正常運行工況下,壓水堆堆芯外90%的集體劑量是由與一回路冷卻劑接觸的管壁上沉積的活化腐蝕產(chǎn)物ACPs(Activated Corrosion Products)引起的。對于水冷聚變堆,不存在裂變產(chǎn)物,ACPs成為放射性的主要來源。無論壓水堆還是水冷聚變堆,ACPs對正常運行工況下的ORE以及事故工況下的潛在放射性釋放都存在著重大影響,直接影響工作人員的照射劑量水平。對ACPs的研究是反應堆事故分析、劑量與輻射防護優(yōu)化、放射性廢物管理等的重要技術(shù)基礎,是反應堆審查取證的重要環(huán)節(jié)。目前國內(nèi)外計算ACPs多數(shù)使用的是經(jīng)驗模型和半經(jīng)驗模型,其應用范圍非常有限,依賴于電廠運行數(shù)據(jù)或試驗數(shù)據(jù),模擬溫度、pH值等參數(shù)限制在一定范圍內(nèi)的變化,只適用于特定的堆型和工況;對放射性核素的種類和核反應的種類有極大的限制,只能計算Co-58、Co-60、Fe-59、Cr-51、Mn-54等幾種放射性核素的核反應,不能滿足聚變堆高能中子輻照下多種材料的源項分析需求,也不能滿足事故瞬態(tài)下短壽命核素的計算需求;聚變堆獨有的脈沖運行特點也對計算提出了新的要求。本論文開發(fā)了基于經(jīng)典的經(jīng)驗模型的水冷反應堆主回路ACPs計算程序。對水冷反應堆主回路ACPs的產(chǎn)生與遷移機理開展研究,建立基于濃度差驅(qū)動原理的機理模型,開發(fā)了基于機理模型的水冷反應堆主回路ACPs計算程序。脫離了對核電廠及試驗回路的經(jīng)驗系數(shù)的依賴,結(jié)合溶解度的計算成功實現(xiàn)了物質(zhì)遷移方向的自動匹配功能,突破了以往程序?qū)Χ研图斑\行工況的限制。借助課題組中的沉積試驗及測量結(jié)果,根據(jù)對模型計算值和試驗測量結(jié)果的分析,對沉積模塊進行修正,成功實現(xiàn)了pH值對沉積行為的影響的模擬;對多種結(jié)構(gòu)材料進行了不同運行環(huán)境下的腐蝕行為模擬試驗,解決了聚變堆工況下腐蝕模型計算不準確的問題;引入EAF-2007數(shù)據(jù)庫,為活化及衰變反應提供核數(shù)據(jù),實現(xiàn)了計算任意放射性核素的功能;加入多種脈沖等效模塊,滿足不同計算需求及聚變堆型的要求,保證計算精度的同時可以大幅提高計算效率;添加點核積分模塊計算相應的劑量率及職業(yè)照射ORE(Occupational Radiation Exposure),實現(xiàn)了活度濃度與劑量率的轉(zhuǎn)換。通過上述工作,克服對pH值變化范圍的限制,突破了以往程序?qū)Σ牧霞肮r、放射性核素種類的限制,直接給出γ劑量場使得計算結(jié)果更加直觀�；谝陨瞎ぷ�,開發(fā)了適用于壓水堆和水冷聚變堆的ACPs計算分析程序CATE。為充分驗證模型的正確性及程序的適用性,分別從試驗驗證和程序驗證兩個角度選取了試驗回路MIT-PCCL回路、水冷聚變堆ITER LIM-OBB回路和壓水堆秦山二期核電廠一回路進行了模擬分析,并與公開發(fā)表的文獻結(jié)果進行了比對。計算結(jié)果均能與試驗測量值和程序計算值保持在同一數(shù)量級,在源項計算領(lǐng)域內(nèi)可以認為計算結(jié)果是吻合的,從試驗和程序的角度驗證了模型的準確性和結(jié)果的可靠性。水冷聚變堆的高溫高壓環(huán)境、產(chǎn)生的高能量中子會對結(jié)構(gòu)材料產(chǎn)生較強的腐蝕、活化作用,水冷聚變堆對結(jié)構(gòu)材料提出了更高的要求,結(jié)合我國已生產(chǎn)的多種低活化材料,應用CATE程序首次實現(xiàn)了國際熱核聚變實驗堆ITER(International Thermonuclear Experimental Reactor)環(huán)境下國產(chǎn)低活化材料及傳統(tǒng)奧氏體不銹鋼對水冷聚變堆ACPs影響的對比分析;當前中國聚變工程試驗堆CFETR(China Fusion Engineering Test Reactor)處于設計階段,ACPs源項的水平是其頒證的關(guān)鍵影響因素,可能對聚變堆設計和運行有很大的影響,目前國內(nèi)尚無對CFETR的ACPs水平計算分析的研究工作,本文應用CATE程序?qū)崿F(xiàn)了對CFETR包層回路的ACPs進行計算分析。
[Abstract]:The radioactive source term relationship reactor system operation, maintenance and decommissioning and other sectors, have a significant impact on the radiation protection, analysis of individual and collective dose and safety. In water reactors, structural materials in contact with the coolant corrosion, formation of oxide layer is stable, metal ions through the oxide layer is released into the coolant. The oxide layer irradiated area and from the coolant carrying metal ions into the irradiated area irradiated by neutron activation reaction as radioactive substances, radioactive substances in the coolant in the coolant carrying deposition to the non irradiated area formed a gamma radiation field of power plant maintenance operation and maintenance personnel constitute radiation hazard. Under normal operating conditions, the collective dose 90% pressure the core is made of activated corrosion products ACPs deposition wall contact with a coolant on (Activated Corrosion Products) for the cause. Water cooled fusion reactor, there is no fission products, ACPs has become the main source of radioactivity. Both PWR or water-cooled fusion reactor under normal operating conditions, ACPs of ORE and the release of potential radioactive accident conditions have significant influence, directly affect the dose level of the staff. The study of ACPs reactor accident analysis dose, radiation protection and optimization, an important technical basis for management of radioactive waste, is an important part of the reactor. The review of evidence at home and abroad ACPs calculation is used mostly empirical and semi empirical models, the application range is very limited, depending on the power plant operation data and the test data, the simulation of temperature, pH value and other parameters change limit in a certain range, only suitable for specific reactor types and conditions; types of radionuclides and nuclear reactions are extremely limited, can only calculate the Co-58 Co-60, Fe-59, Cr-51, Mn-54 and other types of nuclear reactions of radionuclides, can not meet the high energy neutron irradiation of various materials in fusion reactor source analysis needs, can not meet the computing needs of short life nuclide transient accident; fusion pulse operation characteristic and puts forward new requirements for the calculation. This paper developed a calculation program the main circuit of water-cooled reactor ACPs empirical model based on the classical research. And the migration mechanism of water cooled reactor main loop of the ACPs was established based on the principle of differential drive mechanism model, a computer program is developed the main circuit of ACPs water cooled reactor based on mechanism model. From the experience dependent coefficient on the nuclear power plant and the test circuit. Automatic matching with the calculated solubility of the successful implementation of the migration direction, broke through the limitations of previous procedures on the reactor type and operating condition. By the research group The deposition of test and measurement results, according to the analysis of the calculated value and the experimental results of the model, the deposition module is modified, the successful implementation of the simulation effect of pH value on the deposition behavior of various structural materials; the corrosion behavior of different operation environment simulation test, solves the corrosion condition of fusion reactor model the problem of inaccurate calculation; introduction of the EAF-2007 database to provide data for the activation and nuclear decay reaction, the calculation of arbitrary radionuclides; adding a variety of pulse equivalent module, to meet the different computational requirements and fusion type requirements, and ensure the calculation accuracy can greatly improve the computational efficiency; calculation of dose rate and irradiation ORE corresponding occupation add the point kernel integral module (Occupational Radiation Exposure), the activity concentration and dose rate conversion. Through the above work, to overcome the pH value range In the limit, breaking the previous program of materials and conditions, radioactive nuclide types, directly given dose field makes the result more intuitionistic. Based on the above work, developed for PWR and water-cooled fusion reactor ACPs analysis the applicability of CATE. program is correct and full program verification model. From the test and verification procedures two angle test circuit MIT-PCCL circuit, ITER circuit and LIM-OBB pressurized water cooled fusion reactor Qinshan two nuclear power plant in a loop are simulated, and the results and the published literature were compared. The calculated results are with the experimental values and the calculated values remain in the same magnitude, that calculation results were consistent with the source term calculation domain, the reliability model and the accuracy of the results is verified by the test program and point of view. Water cooled fusion reactor The environment of high temperature and high pressure, high energy neutrons produced by strong corrosion of structural materials, activation, water-cooled fusion reactor has put forward higher requirements for structural materials, combined with a variety of production in China has low activation materials, application of CATE ITER for the first time the International Thermonuclear Experimental Reactor (International Thermonuclear Experimental Reactor) under the environment of domestic low activation of contrast material and traditional austenitic stainless steel pile of ACPs impact on water cooled fusion analysis; current China Fusion Engineering Test Reactor (CFETR China Fusion Engineering Test Reactor) in the design stage, ACPs source level is the key factor affecting the certification, may have a great impact on the fusion reactor design and operation, at present there is no domestic level of CFETR ACPs calculation and analysis of the research work, the application of CATE program on CFETR clad ACPs gauge circuit Calculation analysis.

【學位授予單位】：華北電力大學(北京)
【學位級別】：博士
【學位授予年份】：2017
【分類號】：TM623.2

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