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A novel approach for radionuclide diffusion in the enclosed environment of a marine nuclear reactor during a severe accident

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Nuclear Science and Techniques 2022年第2期33卷 53-65页

作者： Fang Zhao Shu-Liang Zou Shou-Long Xu Xuan Wang Jun-Long Wang De-Wen Tang School of Resource Environment and Safety Engineering University of South ChinaHengyang 421001China Hunan Provincial Key Laboratory of Emergency Safety Technology and Equipment for Nuclear Facilities Hengyang 421001China Shanghai Nuclear Engineering Research and Design Institute Co.LTD Shanghai 200000China Science and Technology On Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu 610213China

A severe accident in a marine nuclear reactor leads to radionuclide leakage,which causes hidden dangers to workers and has adverse effects of environmental *** is necessary to propose a novel approach to radionuclide diffusion in a confined environment after a severe accident in a marine nuclear ***,this study proposes a new method for the severe accident analysis program MELCOR coupled with computational fluid dynamics scSTREAM to study radioactive diffusion in severe *** radionuclide release fraction and temperature calculated by MELCOR were combined with the scSTREAM calculations to study the radionuclide diffusion behavior and the phenomenon of radionuclide diffusion in different space environments of the reactor under the conditions of varying wind velocities of the ventilation system and diffusion *** results show that the wind velocity of the ventilation system is very small or zero,and the turbulent diffusion of radionuclides is not obvious and diffuses slowly in the form of condensation sedimentation and gravity *** the wind speed of the ventilation system increases,the flow of radionuclides meets the wall and forms eddy currents,affecting the time variation of radionuclides diffusing into chamber *** wind velocity of the ventilation system and the diffusion speed has opposite effects on the time variation trend of radionuclide diffusion into the four chambers.

关键词： Radionuclide diffusion MELCOR coupled with scSTREAM severe accident Marine nuclear reactor

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Influence of active and passive equipment for advanced pressurized water reactor on thermal hydraulic and source term behavior in severe accidents

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Energy Storage and Saving 2023年第1期2卷 392-402页

作者： Jishen Li Bin Zhang School of Nuclear Science and Technology Xi’an Jiaotong UniversityXi’an710049China State Key Laboratory of Multiphase Flow in Power Engineering Xi’an Jiaotong UniversityXi’an710049China

Extensive studies have been carried out on the behavior of core degradation and fission products of common pressurized water reactors(PWRs).However,few of them have investigated the relationship between thermal hydraulic and fission product behavior in advanced passive *** to the impact of thermal hydraulic be-haviors in different accident sequences on the release and transportation of fission products,an integrated severe accident analysis(ISAA)code with highly coupled thermal hydraulic and source term calculations is required to simultaneously analyze thermal hydraulic and source term *** advanced passive PWRs,important safety systems that may affect the behavior of the core and fission products should be *** is therefore necessary to simulate the thermal hydraulic and fission product behavior of advanced passive *** this study,the ISAA code is adopted to simulate the occurrence of a hypothetical double ended cold leg LBLOCA of HPR1000 in three scenarios of equipment *** results show that the high-temperature fuel rods and cladding ma-terials exhibit delayed failure at the lower position of the active core,whereas earlier failure at higher position during the *** and passive equipment affects fuel temperature,the oxidation conditions of the fuel,the interaction of fission products and structural materials,and the state of the fuel,thereby affecting the release of fission products in the ***1000 only relies on passive equipment to relieve the core degradation in severe accidents,realize the in-vessel retention of melt,and eliminate the ex-vessel release possibility of fission *** is hoped that the results can provide references for HPR1000 to formulate the severe accident management guidelines(SAMG).

关键词： Nuclear safety LBLOCA severe accident Source term HPR1000 Active and passive equipment

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Analysis of molten metal spreading and solidification behaviors utilizing moving particle full-implicit method

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Frontiers in Energy 2021年第4期15卷 959-973页

作者： Ryo YOKOYAMA Masahiro KONDO Shunichi SUZUKI Koji OKAMOTO Department of Nuclear Engineering and Management The University of Tokyo7-3-1 HongoBunkyo-kuTokyo 113-8656Japan Research Center for Computational Design of Advanced Functional materials(CD-FMat) Department of Materials and ChemistryNational Institute of Advanced Industrial Science and Technology(AIST)Central 21-1-1UmezonoTsukubaIbaraki 305-8568Japan Institute of Engineering Innovation School of EngineeringThe University of Tokyo7-3-1 HongoBunkyo-kuTokyo 113-8656Japan Nuclear Professional School The University of Tokyo2-22 ShirakataTokai-muraIbaraki 319-1188Japan

To retrieve the fuel debris in Fukushima Daiichi Nuclear Power Plants(1F),it is essential to infer the fuel debris *** particular,the molten metal spreading behavior is one of the vital phenomena in nuclear severe accidents because it determines the initial condition for further accident scenarios such as molten core concrete interaction(MCCI).In this study,the fundamental molten metal spreading experiments were performed with different outlet diameters and sample amounts to investigate the effect of the outlet for spreading-solidification *** the numerical analysis,the moving particle full-implicit method(MPFI),which is one of the particle methods,was applied to simulate the spreading *** the MPFI framework,the melting-solidification model including heat transfer,radiation heat loss,phase change,and solid fraction-dependent viscosity was developed and *** addition,the difference in the spreading and solidification behavior due to the outlet diameters was reproduced in the *** simulation results reveal the detailed solidification procedure during the molten metal *** is found that the viscosity change and the solid fraction change during the spreading are key factors for the free surface condition and solidified ***,it is suggested that the MPFI method has the potential to simulate the actual nuclear melt-down phenomena in the future.

关键词： molten metal spreading solidification particle method severe accident fuel debris decommissioning

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Improvement of solidification model and analysis of 3D channel blockage with MPS method

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Frontiers in Energy 2021年第4期15卷 946-958页

作者： Reo KAWAKAMI Xin LI Guangtao DUAN Akifumi YAMAJI Isamu SATO Tohru SUZUKI Cooperative Major in Nuclear Energy Graduate School and Advanced Science and EngineeringFaculty of Science and EngineeringWaseda University3-4-1 OkuboShinjuku-kuTokyo169-8555Japan Department of Nuclear Engineering and Management The University of Tokyo7-3-1 HongoBunkyo-kuTokyo113-8656Japan Department of Nuclear Safety Engineering Faculty of EngineeringTokyo City University1-28-1 TamazutsumiSetagaya-kuTokyo158-0087Japan

In a severe accident of a nuclear power reactor,coolant channel blockage by solidified molten core debris may significantly influence the core degradations that *** moving particle semi-implicit(MPS)method is one of the Lagrangian-based particle methods for analyzing incompressible *** the study described in this paper,a novel solidification model for analyzing melt flowing channel blockage with the MPS method has been developed,which is suitable to attain a sufficient numerical accuracy with a reasonable calculation *** prompt velocity diffusion by viscosity is prioritized over the prompt velocity correction by the pressure term(for assuring incompressibility)within each time step over the“mushy zone”(between the solidus and liquidus temperature)for accurate modeling of solidification before fixing the coordinates of the completely solidified *** sustain the numerical accuracy and stability,the corrective matrix and particle shifting techniques have been applied to correct the discretization errors from irregular particle arrangements and to recover the regular particle arrangements,*** validate the newly developed algorithm,2-D benchmark analyses are conducted for steady-state freezing of the water in a laminar flow between two parallel ***,3-D channel blockage analyses of a boiling water reactor(BWR)fuel support piece have been *** results show that a partial channel blockage develops from the vicinity of the speed limiter,which does not fully develop into a complete channel blockage,but still diverts the incoming melt flow that follows to the orifice region.

关键词： boiling water reactor(BWR) severe accident channel blockage moving particle semi-implicit(MPS)method solidification*

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THAI experimental research on hydrogen risk and source term related safety systems

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Frontiers in Energy 2021年第4期15卷 887-915页

作者： Sanjeev GUPTA Martin FREITAG Gerhard POSS Becker Technologies GmbH Rahmannstrasse 11Eschborn 65760Germany

In the defense-in-depth concept employed for the safety of nuclear installations,maintaining integrity of containment as the last barrier is of high importance to limit the release of radioactivity to the environment in case of a severe *** active and passive safety systems implemented in containments of light water reactors(LWRs)are designed to limit the consequences of such *** the performance and reliability of such systems under accident conditions is critical to the safety of nuclear *** the aftermath of the Fukushima accident,there has been focus on re-examining the existing safety systems to demonstrate their capabilities for a broader range of boundary conditions comprising both the early as well as the late phases of an *** addition to the performance testing of safety systems,their interaction with containment atmosphere needs detailed investigations to evaluate the effects of operation of safety systems on H2 risk and fission product(FP)behavior in containment,which may ultimately have an impact on the source term to the *** this context,an extensive containment safety related experimental research has been conducted in a thermalhydraulics,hydrogen,aerosols,and iodine test facility(THAI,60 m3,single vessel)/(THAI+,80 m3,two interconnected vessels).Related to the subject of this paper,experimental investigations covered performance testing of various safety and mitigation systems,i.e.,containment spray,passive autocatalytic recombiner(PAR),pressure suppression pool(water pools),and effects of their operation on H2 risk and in-containment FP *** experimental results have provided a better phenomenological understanding and database for validation and further improvement of a safety analysis tool based on computation fluid dynamic(CFD)and lumped parameter(LP)modeling *** paper summarizes the main insights obtained from the aforesaid THAI experimental research covering safety systems

关键词： severe accident containment safety mitigation H2 risk source term

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Moving particle semi-implicit simulation on the molten Wood's metal downward relocation process

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Nuclear Science and Techniques 2021年第8期32卷 110-121页

作者： Anni Nuril Hidayati Abdul Waris Asril Pramutadi Andi Mustari Dwi Irwanto Nur Asiah Aprianti Department Faculty of Mathematics and Natural ScienceInstitut Teknologi BandungJalan Ganesha 10Bandung 40132Indonesia Nuclear Physics and Biophysics Research Division Physics DepartmentFaculty of Mathematics and Natural ScienceInstitut Teknologi BandungJalan Ganesha 10Bandung 40132Indonesia

In the case of a severe accident involving nuclear reactors,an important aspect that should be considered is the leakage of molten material from the inside of the reactor into the *** molten materials damage other reactor components,such as electrical tubes,grid plates and core *** this study,the moving particle semi-implicit(MPS)method is adopted and improved to analyze the twodimensional downward relocation process of molten Wood’s metal as a representation of molten material in a nuclear *** molten material impinges the Wood’s metal plate(WMP),which is mounted on a rigid dummy stainless steel in a cylindrical test *** breaching process occurs because of heat transfer between the molten material and *** formed breach areas were in good agreement with the experimental results,and they showed that the molten Wood’s metal spread above the *** solid WMP fraction decreased with time until it reached the termination time of the *** present results show that the MPS method can be applied to simulate and analyze the downward relocation process of molten material in the grid plate of a nuclear reactor.

关键词： Heat transfer Moving particle semi-implicit Phase change Relocation severe accident

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Experimental Investigation on Fuel Coolant Interaction Using Simulant Ceramic Melts in Water: Insights and Conclusions

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World Journal of Nuclear Science and Technology 2020年第4期10卷 139-157页

作者： Nitendra Singh Arun K. Nayak Parimal P. Kulkarni Homi Bhabha National Institute Mumbai India Bhabha Atomic Research Centre Reactor Engineering Division Mumbai India

Steam explosion is one of the crucial and poorly understood phenomena which may occur during severe accident scenario and may lead to containment failure. In spite of several experimental and analytical studies, the root cause of steam explosion has not been understood. Recent claims in the literature suggest that the presence of fine fragmentation during steam explosion causes its occurrence. In order to investigate this and understand the root cause of steam explosion, series of experiments were performed with 50 g to 2500 g of CaO-B2O3, a corium simulant in 4.5 litre of water. It was observed that steam explosion may occur even in the absence of fine fragments, which is contrary to the claims in the literature. To investigate further, conversion efficiency analysis was performed. This suggested that the amount of thermal energy converted to mechanical energy is more important deciding factor in explaining the occurrence of steam explosion. The present study discusses the importance of conversion efficiency in deciding steam explosion and also gives a new perspective to look at steam explosion phenomenology.

关键词： severe accident Core Catcher Steam Explosion Fuel Coolant Interaction Fragmentation

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Nuclear power plant life extension:How aging affects performance of containments & other structures

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Engineering Sciences 2013年第3期11卷 39-52页

作者： Robert A Dameron Sun Junling Moffatt & Nichol Inc. Sun Engineering Consultants International Inc.

This paper focuses on how aging can affect performance of safety-related structures in nuclear power plant (NPP). Knowledge and assessment of impacts of aging on structures are essential to plant life extension analysis,especially performance to severe loadings such as loss-of-coolant-accidents or major seismic events. Plant life extension issues are of keen interest in countries (like the United States) which have a large,aging fleet of NPPs. This paper addresses the overlap and relationship of structure aging to severe loading performance,with particular emphasis on containment structures.

关键词： NPP structure performance plant life extension finite element analysis corrosion containment severe accident seismic event

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Analysis of Pb-Bi Vessel Wall Ablation Experiment with High Temperature Liquid by MPS Method

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Journal of Energy and Power Engineering 2015年第11期9卷 944-954页

作者： Daisuke Masumura Akifumi Yamaji Masahiro Furuya Cooperative Major in Nuclear Energy Graduate School of Advanced Science and Engineering Faculty of Science andEngineering Waseda University Tokyo 169-8555 Japan Nuclear Technology Research Laboratory Central Research Institute of Electric Power Industry Tokyo 201-8511 Japan

In a severe accident of a light water reactor, ablation of the RPV （reactor pressure vessel） lower head by corium is a key phenomenon, which affects progression of the accident. The MPS （moving particle semi-implicit） method is one of particle methods that calculate behavior of incompressible fluid by semi-implicit method. In preceding studies, the MPS method has been extensively studied and developed for simulations of different phenomena involved in severe accident of nuclear reactors. This paper aims to investigate whether the MPS method is capable of analyzing the lower head ablation phenomenon. The small-scale experiment carried out at CRIEPI （Central Research Institute of Electric Power Industry） using Pb-Bi vessel and silicone oil was analyzed for the validation of the MPS method. The MPS analysis well reproduced the experimental phenomena qualitatively. However, with respect to some quantitative results, more investigation such as influence of the calculation particle size is necessary.

关键词： severe accident ablation particle method the MPS method stratification.

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Analysis of QUENCH-ACM Experiments Using SCDAP/RELAP5

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Journal of Energy and Power Engineering 2011年第10期5卷 918-927页

作者： J. Birchley J. Stuckert Paul Seherrer Institute Villigen 5232 Switzerland Karlsruhe Institute of Technology Karlsruhe D76021 Germany

The QUENCH experimental programme at Karlsruhe under severe accident conditions, but while the geometry is still Institute of Technology investigates heat-up and reflooding of a core mainly rod-like. The recent QUENCH-ACM series of experiments, comprising QUENCH-12 （El 10 cladding alloy）, -14 （M5 alloy） and -15 （Zirlo^TM alloy）, together with QUENCH-06 （reference case, Zircaloy-4 alloy） addressed the effect of alternative cladding materials on oxidation and quenching under similar conditions. Superficial inspection of the experimental results reveals only minor differences in the thermal and oxidation response, except for the much larger hydrogen release during reflood in QUENCH-12. Post-test calculations were performed using a version of SCDAP/RELAP5/MOD3.2, modified to represent the QUENCH facility and to invoke alternative oxidation correlations. The calculations agreed rather well with experiments QUENCH-06, -14 and -15, but the significant hydrogen release during reflood in QUENCH-12 was not captured. Closer examination of the experimental results reveals further differences between QUENCH-12 which may be linked to breakaway oxidation of the E110 cladding. The analyses support the heuristic observation that there was no major difference between the influence of Zircaloy-4, M5 or ZirloTM, but the E-110 exhibited a contrasting behaviour with a consequent impact on the reflooding.

关键词： severe accident reflood oxidation kinetic cladding alloy computer codes.

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