1-20 of 55
Keywords: severe accident
Close
Follow your search
Access your saved searches in your account

Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Proceedings Papers

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A011, August 4–6, 2021
Paper No: ICONE28-64252
...Abstract Abstract The aerosol removal mechanism and capacity related to passive containment cooling system (PCS) for PWR reactors during the severe accident is an important and interesting topic among researchers, which can enhance the natural removal of suspended aerosols, reducing...
Proceedings Papers

Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T12A023, August 4–6, 2021
Paper No: ICONE28-64417
... to model and analyze the severe accident of IP200 reactor caused by SBLOCA superimposed by the emergency power failure. Based on the steady state calculation, which agrees well with designed values, the SBLOCA accident for transient calculation started. First, the SBLOCA accident without the passive core...
Topics: Accidents
Proceedings Papers

Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T12A003, August 4–6, 2021
Paper No: ICONE28-62252
... became small when the B 4 C concentration against SS decreased. Moreover, it was confirmed that the liquid phase reaction feature of SS-SS with certain B 4 C concentration is still dominant in comparison with that of B 4 C-SS at low temperatures. sodium-cooled fast reactor severe accident...
Proceedings Papers

Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T12A016, August 4–6, 2021
Paper No: ICONE28-64246
... injection. During this dry period, in-vessel and ex-vessel debris were heat up and it took another four days to re-flood the heated up debris. severe accident Fukushima Daiichi nuclear power plant unit 3 ex-vessel debris dryout re-flooding decommissioning Proceedings of the 2021 28th...
Proceedings Papers

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A023, August 4–6, 2021
Paper No: ICONE28-64152
...Abstract Abstract The purpose of the present study is to evaluate and improve the capability of the SIMMER code to demonstrate severe accident mitigation in Sodium-cooled Fast Reactors (SFR). Here the numerical representation of the mitigation strategy with controlled material transfer...
Proceedings Papers

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A052, August 4–6, 2021
Paper No: ICONE28-64541
...Abstract Abstract Advanced SMRs such as the integrated pressurized water reactor IP200 use different design in the systems, structures, components from large reactors for achieving a high level of safety and reliability. In this thesis, the IP200 severe accident induced by the SBO and emergency...
Proceedings Papers

Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T04A005, August 4–6, 2021
Paper No: ICONE28-64162
... the viewpoint of achieving natural circulation cooling after ZrO2), which contains some neutron absorbing material reactor shutdown. However, consequences of severe accident of (tentatively, B4C) is placed at the center of the lower plenum to such SMR class Super FR has never been considered. Two major disperse...
Proceedings Papers

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A020, August 4–6, 2021
Paper No: ICONE28-64614
... to understand the progress of the accidents and evaluate the effectiveness of the safety Keywords: Severe accident, Molten metal, Spreading measures. However, the models which describe the after-core behavior, Wet condition meltdown are still affected by significant uncertainty. Continuous effort is required...
Proceedings Papers

Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T12A027, August 4–6, 2021
Paper No: ICONE28-64540
... simulations. Moreover, Development Project of Japan. A part of this study is the result the following issues should be considered: of Understanding Mechanisms of Severe Accidents and Improving Safety of Nuclear Reactors by Computer Science of (1) Calculation cost and efficiency The current validation...
Proceedings Papers

Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T12A006, August 4–6, 2021
Paper No: ICONE28-63285
... Proceedings of the 2021 28th International Conference on Nuclear Engineering ICONE28 August 4-6, 2021, Virtual, Online ICONE28-63285 ANALYSES OF WET AND DRY CAVITY STRATEGIES FOR BWR SEVERE ACCIDENT MANAGEMENT WITH MELCOR-2.2 Ayato Takashima1, Akifumi Yamaji1, Xin Li1, Daisuke Fujiwara2, Hiroshi...
Proceedings Papers

Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T11A012, August 4–6, 2021
Paper No: ICONE28-65129
... assembly during the CLADS-MADE-02 test, where the conditions of the 1F Unit 3 was simulated. Interesting features emerged in an oxidative environment. BWR severe accident Fukushima-1 decommissioning control blade degradation B 4 C Proceedings of the 2021 28th International Conference...
Proceedings Papers

Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T12A021, August 4–6, 2021
Paper No: ICONE28-64403
...Abstract Abstract After the Fukushima accident, the disposal of radioactive liquid waste has received great attention. The analysis of nuclide activity in the liquid waste of the containment after a severe accident is the prerequisite for the treatment of the liquid waste. Based on the source...
Proceedings Papers

Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T12A029, August 4–6, 2021
Paper No: ICONE28-64611
... suppression system are designed in the plant. Three severe accident mitigation measures, i.e., the pressurizer (PZR) relief extension, the external vessel reactor cooling (EVRC) and the Passive autocatalystic recombiners (PAR) are set up to actually eliminate the large release of radioactive products...
Proceedings Papers

Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T09A006, August 4–6, 2021
Paper No: ICONE28-64749
... to the accident. Especially after the Fukushima nuclear accident, the uncertainty of severe accidents [1, 2], it is difficult to carry out nuclear industry and nuclear safety regulatory authorities have software verification for it. There are plenty of verification paid more attention to the study of severe...
Proceedings Papers

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A003, August 4–6, 2021
Paper No: ICONE28-61490
... and Information Faculty of Engineering, Information and Systems, Engineering, University of Tsukuba University of Tsukuba Tsukuba, Ibaraki, Japan Tsukuba, Ibaraki, Japan ABSTRACT NOMENCLATURE Understanding radioactive aerosol behavior is important during severe accidents in nuclear power plants. In particular...
Proceedings Papers

Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T01A003, August 4–5, 2020
Paper No: ICONE2020-16236
...Abstract Abstract Vessel penetrations are important features of both pressurized water reactors and boiling water reactors. The thermal and structural behaviour of instrumentation guide tubes (IGTs) and control rod guide tubes (CRGTs) during a severe accident is vital in the assessment...
Proceedings Papers

Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T03A005, August 4–5, 2020
Paper No: ICONE2020-16213
...Abstract Abstract In the severe accident (SA) of nuclear reactors, fuel and components melt, and melted materials fall to a lower part of a reactor vessel. In the lower part of a reactor vessel, in some sections of the SAs, it is considered that there is a water pool. Then, the melted core...
Proceedings Papers

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A041, August 4–5, 2020
Paper No: ICONE2020-16470
.... Keywords: Severe accident; Corium pool structure; In- Vessel Retention; Critical Heat Flux; MAAP5 code Nomenclature M Mass, kg n mole fraction N molar mass, kg/mol q average heat flux, W/m2 k thermal conductivity, W/(mK) H height, m Nu Nusselt number Ra Reynolds number T temperature, K density, kg/m3...
Proceedings Papers

Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T03A021, August 4–5, 2020
Paper No: ICONE2020-16817
...Abstract Abstract In order to contribute the improvement of estimation accuracy for severe accident code such as SAMPSON, we have developed the chemical reaction model such as eutectic reaction and oxidation in micro scale, e.g., B 4 C-SUS in the control rod blade and UO 2 -Zry in fuel rods...
Proceedings Papers

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A004, August 4–5, 2020
Paper No: ICONE2020-16075
... interdiffusion behavior in the early stage of the eutectic melting. sodium-cooled fast reactor severe accident eutectic melting kinetic behavior thermal analysis STUDY ON EUTECTIC MELTING BEHAVIOR OF CONTROL ROD MATERIALS IN CORE DISRUPTIVE ACCIDENTS OF SODIUM-COOLED FAST REACTORS: (3) KINETIC STUDY...