• 제목/요약/키워드: safety net

검색결과 1,566건 처리시간 0.023초

Preconditioned Jacobian-free Newton-Krylov fully implicit high order WENO schemes and flux limiter methods for two-phase flow models

  • Zhou, Xiafeng;Zhong, Changming;Li, Zhongchun;Li, Fu
    • Nuclear Engineering and Technology
    • /
    • 제54권1호
    • /
    • pp.49-60
    • /
    • 2022
  • Motivated by the high-resolution properties of high-order Weighted Essentially Non-Oscillatory (WENO) and flux limiter (FL) for steep-gradient problems and the robust convergence of Jacobian-free Newton-Krylov (JFNK) methods for nonlinear systems, the preconditioned JFNK fully implicit high-order WENO and FL schemes are proposed to solve the transient two-phase two-fluid models. Specially, the second-order fully-implicit BDF2 is used for the temporal operator and then the third-order WENO schemes and various flux limiters can be adopted to discrete the spatial operator. For the sake of the generalization of the finite-difference-based preconditioning acceleration methods and the excellent convergence to solve the complicated and various operational conditions, the random vector instead of the initial condition is skillfully chosen as the solving variables to obtain better sparsity pattern or more positions of non-zero elements in this paper. Finally, the WENO_JFNK and FL_JFNK codes are developed and then the two-phase steep-gradient problem, phase appearance/disappearance problem, U-tube problem and linear advection problem are tested to analyze the convergence, computational cost and efficiency in detailed. Numerical results show that WENO_JFNK and FL_JFNK can significantly reduce numerical diffusion and obtain better solutions than traditional methods. WENO_JFNK gives more stable and accurate solutions than FL_JFNK for the test problems and the proposed finite-difference-based preconditioning acceleration methods based on the random vector can significantly improve the convergence speed and efficiency.

Explore the possible advantages of using thorium-based fuel in a pressurized water reactor (PWR) Part 1: Neutronic analysis

  • Galahom, A. Abdelghafar;Mohsen, Mohamed Y.M.;Amrani, Naima
    • Nuclear Engineering and Technology
    • /
    • 제54권1호
    • /
    • pp.1-10
    • /
    • 2022
  • This study discusses the effect of using 232Th instead of 238U on the neutronic characteristics and the main operating parameters of the pressurized water reactor (PWR). MCNPX version 2.7 was used to compare the neutronic characteristics of UO2 with (Th, 235U)O2 and (Th, 233U) O2. Firstly, the infinity multiplication factor (Kinf), thermal neutron flux, and power distribution have been studied for the investigated fuel types. Secondly, the effect of Gd2O3 and Er2O3 on the Kinf and on the radial thermal neutron flux and thermal power has been investigated to distinguish which of them is more suitable than the other in reactivity management. Thirdly, to illustrate the effectiveness of 232Th in decreasing the inventory of both the actinides and non-actinides, the concentration of plutonium (Pu) isotopes and minor actinides (MAs) has been simulated with the fuel burnup. Besides, due to their large thermal neutron absorption cross-section, the concentrations of 135Xe, 149Sm, and 151Sm with the fuel burnup have been investigated. Finally, the main safety parameters such as the reactivity worth of the control rods (ρCR), the effective delayed neutron fraction βeff, and the Doppler reactivity coefficient (DRC) were calculated to determine to which extent these fuel types achieve the acceptable limits.

Design and analysis of isolation effectiveness for three-dimensional base-seismic isolation of nuclear island building

  • Zhu, Xiuyun;Lin, Gao;Pan, Rong;Li, Jianbo
    • Nuclear Engineering and Technology
    • /
    • 제54권1호
    • /
    • pp.374-385
    • /
    • 2022
  • In order to investigate the application of 3D base-seismic isolation system in nuclear power plants (NPPs), comprehensive analysis of constitution and design theory for 3-dimensional combined isolation bearing (3D-CIB) was presented and derived. Four different vertical stiffness of 3D-CIB was designed to isolate the nuclear island (NI) building. This paper aimed at investigating the isolation effectiveness of 3D-CIB through modal analysis and dynamic time-history analysis. Numerical results in terms of dynamic response of 3D-CIB, relative displacement response, acceleration and floor response spectra (FRS) of the superstructure were compared to validate the reliability of 3D-CIB in mitigating seismic response. The results showed that 3D-CIB can significantly attenuate the horizontal acceleration response, and a fair amount of the vertical acceleration response reduction of the upper structure was still observed. 3D-CIB plays a significant role in reducing the horizontal and vertical FRS, the vertical FRS basically do not vary with the floor height. The smaller the vertical stiffness of 3D-CIB is, the better the vertical isolation effectiveness is, whereas, it will increase the displacement and the rocking effect of superstructure. Although the advantage of 3D-CIB is that the vertical stiffness can be flexibly adjusted, it should be designed by properly accounting for the balance between the isolation effectiveness and displacement control including rocking effect. The results of this study can provide the technical basis and guidance for the application of 3D-CIB to engineering structure.

Study on the effect of long-term high temperature irradiation on TRISO fuel

  • Shaimerdenov, Asset;Gizatulin, Shamil;Dyussambayev, Daulet;Askerbekov, Saulet;Ueta, Shohei;Aihara, Jun;Shibata, Taiju;Sakaba, Nariaki
    • Nuclear Engineering and Technology
    • /
    • 제54권8호
    • /
    • pp.2792-2800
    • /
    • 2022
  • In the core of the WWR-K reactor, a long-term irradiation of tristructural isotopic (TRISO)-coated fuel particles (CFPs) with a UO2 kernel was carried out under high-temperature gas-cooled reactor (HTGR)-like operating conditions. The temperature of this TRISO fuel during irradiation varied in the range of 950-1100 ℃. A fission per initial metal atom (FIMA) of uranium burnup of 9.9% was reached. The release of gaseous fission products was measured in-pile. The release-to-birth ratio (R/B) for the fission product isotopes was calculated. Aspects of fuel safety while achieving deep fuel burnup are important and relevant, including maintaining the integrity of the fuel coatings. The main mechanisms of fuel failure are kernel migration, silicon carbide corrosion by palladium, and gas pressure increase inside the CFP. The formation of gaseous fission products and carbon monoxide leads to an increase in the internal pressure in the CFP, which is a dominant failure mechanism of the coatings under this level of burnup. Irradiated fuel compacts were subjected to electric dissociation to isolate the CFPs from the fuel compacts. In addition, nondestructive methods, such as X-ray radiography and gamma spectrometry, were used. The predicted R/B ratio was evaluated using the fission gas release model developed in the high-temperature test reactor (HTTR) project. In the model, both the through-coatings of failed CFPs and as-fabricated uranium contamination were assumed to be sources of the fission gas. The obtained R/B ratio for gaseous fission products allows the finalization and validation of the model for the release of fission products from the CFPs and fuel compacts. The success of the integrity of TRISO fuel irradiated at approximately 9.9% FIMA was demonstrated. A low fuel failure fraction and R/B ratios indicated good performance and reliability of the studied TRISO fuel.

Assessment of natural radionuclides and heavy metals contamination to the environment: Case study of Malaysian unregulated tin-tailing processing industry

  • Rahmat, Muhammad Abdullah;Ismail, Aznan Fazli;Rodzi, Nursyamimi Diyana;Aziman, Eli Syafiqah;Idris, Wan Mohd Razi;Lihan, Tukimat
    • Nuclear Engineering and Technology
    • /
    • 제54권6호
    • /
    • pp.2230-2243
    • /
    • 2022
  • The tin tailing processing industry in Malaysia has operated with minimal regard and awareness for material management and working environment safety, impacting the environment and workers in aspects of radiation and heavy metal exposure. RIA was conducted where environmental samples were analyzed, revealing concentrations of 226Ra, 232Th and 40K between the range of 0.1-10.0, 0.0-25.7, and 0.1-5.8 Bq/g respectively, resulting in the AED exceeding UNCEAR recommended value and regulation limit enforced by AELB (1 mSv/y). Raeq calculated indicates that samples collected pose a significant threat to human health from gamma-ray exposure. Assessment of heavy metal content via pollution indices of soil and sediment showed significant contamination and enrichment from processing activities conducted. As and Fe were two of the highest metals exposed both via soil ingestion with an average of 4.6 × 10-3 mg/kg-day and 1.4 × 10-4 mg/kg-day, and dermal contact with an average of 5.6 × 10-4 mg/kg-day and 6.0 × 10-4. mg/kg-day respectively. Exposure via accidental ingestion of soil and sediment could potentially cause adverse non-carcinogenic and carcinogenic health effect towards workers in the industry. Correlation analysis indicates the presence of a relationship between the concentration of NORM and trace elements.

Improvement Measures for Projects Subject to Environmental Impact Assessment in Urban Areas

  • CHO, Dong-Myung;LEE, Ju-Yeon;KWON, Woo-Taeg
    • 웰빙융합연구
    • /
    • 제5권2호
    • /
    • pp.43-50
    • /
    • 2022
  • Purpose: The small-scale environmental impact assessment conducted during the development project stage has focused on the preservation of the natural environment centered on non-urban areas, due to the nature of urbanization, health problems for citizens of high-density urban areas have a limitation in that they are relatively neglected. In the case of strategic environmental impact assessment and environmental impact assessment in urban areas, there is no basis for evaluation in urban areas because there are exceptions to be excluded from the target projects or there are no target project regulations for buildings. Therefore, in this research, we examined the problems with the target project such as the current environmental impact assessment, and tried to establish a system improvement plan that can solve them. Research design, data and methodology: After reviewing the current environmental impact assessment-related laws (including enforcement ordinances) and national land planning laws (including enforcement ordinances), exceptions such as environmental impact assessment in urban areas were identified and problems were identified. Based on this, an amendment to the Enforcement Decree was proposed to provide institutional support for the expansion of target projects such as environmental impact assessment in urban areas. Results and Conclusions: Through this research, it is expected that the projects subject to environmental impact assessment on development projects in urban areas directly related to the health of the people will be expanded, and the net function of the environmental impact assessment system will be maximized.

SEINA: A two-dimensional steam explosion integrated analysis code

  • Wu, Liangpeng;Sun, Ruiyu;Chen, Ronghua;Tian, Wenxi;Qiu, Suizheng;Su, G.H.
    • Nuclear Engineering and Technology
    • /
    • 제54권10호
    • /
    • pp.3909-3918
    • /
    • 2022
  • In the event of a severe accident, the reactor core may melt due to insufficient cooling. the high-temperature core melt will have a strong interaction (FCI) with the coolant, which may lead to steam explosion. Steam explosion would pose a serious threat to the safety of the reactors. Therefore, the study of steam explosion is of great significance to the assessment of severe accidents in nuclear reactors. This research focuses on the development of a two-dimensional steam explosion integrated analysis code called SEINA. Based on the semi-implicit Euler scheme, the three-phase field was considered in this code. Besides, the influence of evaporation drag of melt and the influence of solidified shell during the process of melt droplet fragmentation were also considered. The code was simulated and validated by FARO L-14 and KROTOS KS-2 experiments. The calculation results of SEINA code are in good agreement with the experimental results, and the results show that if the effects of evaporation drag and melt solidification shell are considered, the FCI process can be described more accurately. Therefore, it is proved that SEINA has the potential to be a powerful and effective tool for the analysis of steam explosions in nuclear reactors.

Natural radioactivity level in fly ash samples and radiological hazard at the landfill area of the coal-fired power plant complex, Vietnam

  • Loan, Truong Thi Hong;Ba, Vu Ngoc;Thien, Bui Ngoc
    • Nuclear Engineering and Technology
    • /
    • 제54권4호
    • /
    • pp.1431-1438
    • /
    • 2022
  • In this study, natural radioactivity concentrations and dosimetric values of fly ash samples were evaluated for the landfill area of the coal-fired power plant (CFPP) complex at Binh Thuan, Vietnam. The average activity concentrations of 238U, 226Ra, 232Th and 40K were 93, 77, 92 and 938 Bq kg-1, respectively. The average results for radon dose, indoor external, internal, and total effective dose equivalent (TEDE) were 5.27, 1.22, 0.16, and 6.65 mSv y-1, respectively. The average emanation fraction for fly ash were 0.028. The excess lifetime cancer risks (ELCR) were recorded as 20.30×10-3, 4.26×10-3, 0.62×10-3, and 25.61×10-3 for radon, indoor, outdoor exposures, and total ELCR, respectively. The results indicated that the cover of shielding materials above the landfill area significantly decreased the gamma radiation from the ash and slag in the ascending order: Zeolite < PVC < Soil < Concrete. Total dose of all radionuclides in the landfill site reached its peak at 19.8 years. The obtained data are useful for evaluation of radiation safety when fly ash is used for building material as well as the radiation risk and the overload of the landfill area from operation of these plants for population and workers.

Study of an improved and novel venturi scrubber configuration for removal of radioactive gases from NPP containment air during severe accident

  • Farooq, Mujahid;Ahmed, Ammar;Qureshi, Kamran;Shah, Ajmal;Waheed, Khalid;Siddique, Waseem;Irfan, Naseem;Ahmad, Masroor;Farooq, Amjad
    • Nuclear Engineering and Technology
    • /
    • 제54권9호
    • /
    • pp.3310-3316
    • /
    • 2022
  • Owing to the rising concerns about the safety of nuclear power plants (NPP), it is essential to study the venturi scrubber in detail, which is a key component of the filtered containment venting system (FCVS). FCVS alleviates the pressurein containment byfiltering and venting out the contaminated air. Themain objective of this research was to perform a CFD investigation of different configurations of a circular, non-submerged, self-priming venturi scrubber to estimate and improve the performance in the removal of elemental iodine from the air. For benchmarking, a mass transfer model which is based on two-film theory was selected and validated by experimental data where an alkaline solution was considered as the scrubbing solution. This mass transfer model was modified and implemented on a unique formation of two self-priming venturi scrubbers in series. Euler-Euler method was used for two-phase modeling and the realizable K-ε model was used for capturing the turbulence. The obtained results showed a remarkable improvement in the removal of radioactive iodine from the air using a series combination of venturi scrubbers. The removal efficiency was improved at every single data point.

지역거점 공공병원의 수익성 결정요인 - COVID-19 유행기간을 중심으로 - (Determinants of Profitability of Regional Public Hospitals in Korea - Focusing on the COVID-19 Pandemic Period -)

  • 지석민;옥현민
    • 한국병원경영학회지
    • /
    • 제27권3호
    • /
    • pp.26-38
    • /
    • 2022
  • Purposes: We analyzed the profitability determinants of regional public hospitals during the entire period between 2010 and 2020 and the period before and after COVID-19. We intended to provide fundamental data for developing publicness evaluation index and task of establishing and expanding regional public hospitals. Methodology: The financial and non-financial information of the regional public hospitals were used as the main analysis data; The financial data was established by the Center for Public Healthcare Policy of National Medical Center, and the non-financial data by the Health Insurance Review and Assessment Service. T-test and regression analysis were used. Findings: The results can be summarized in two. First, the main determinants of profitability of the regional public hospitals were appeared to be the total asset turnover rate and the labor cost rate. Second, during the COVID-19 pandemic in the regional public hospitals, the number of sickbeds, the number of isolation rooms, the total asset turnover rate and the labor cost rate appeared to be the factor worsening the profitability. Practical Implication: The results of this study suggests that the management of the regional public hospitals is not aiming for the profit making, but it performs the functions as the community healthcare safety net such as controlling infectious diseases.