scholarly journals Karakterisasi Hidrogeologi Daerah Sekitar Tapak PLTN di Bengkayang, Kalimantan Barat

EKSPLORIUM ◽  
2021 ◽  
Vol 42 (2) ◽  
pp. 99
Author(s):  
Adi Gunawan Muhammad ◽  
Rachman Fauzi ◽  
Adhika Junara Karunianto ◽  
Wira Cakrabuana ◽  
Widodo Widodo
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Geological Mapping ◽  
Radioactive Material ◽  
Integrated Analysis ◽  
Electrode Arrays ◽  
Alluvial Deposits ◽  
Geomorphological Mapping ◽  
Site Evaluation ◽  
Water Saturated

ABSTRAK. Evaluasi tapak merupakan tahap penting dalam penentuan lokasi calon tapak PLTN skala komersial di Indonesia. Aspek–aspek yang dikaji dalam evaluasi tapak berdasarkan peraturan yang berlaku antara lain aspek geoteknik dan aspek dispersi zat radioaktif. Untuk mendukung kajian aspek tersebut maka perlu adanya kajian karakterisasi hidrogeologi daerah sekitar tapak. Tujuan penelitian ini adalah menentukan karakteristik hidrogeologi daerah sekitar tapak PLTN di Kabupaten Bengkayang, Provinsi Kalimantan Barat berdasarkan aspek geologi dan geofisika. Metode yang dilakukan adalah pemetaan geomorfologi, pemetaan geologi, pemetaan hidrogeologi, pengukuran geolistrik, serta analisis terpadu. Secara morfologi, daerah penyelidikan dibagi menjadi tiga satuan, yaitu dataran aluvial, bukit terisolasi, dan dataran pantai. Secara stratigrafi, satuan batuan yang ditemukan berurutan dari tua ke muda adalah andesit, granodiorit, diorit, endapan pasir kuarsa, endapan pantai, dan endapan aluvial. Pengukuran geofisika menggunakan metode geolistrik dilakukan pada 12 lintasan dengan masing-masing panjang lintasan 470 m dan spasi elektroda 10 m. Pada penampang geolistrik ditemukan beberapa anomali pada kompleks batuan beku yang mengalami frakturasi atau tubuh diorit yang menerobos satuan andesit. Nilai anomali ini berkisar antara 300 Ωm dan >8000 Ωm. Nilai resistivitas yang sangat rendah (<30 Ωm) diinterpretasikan sebagai endapan aluvial yang jenuh air dengan ketebalan mencapai ±100 m. Daerah penelitian dapat dibagi menjadi tiga satuan hidrogeologi; akuifer dengan aliran melalui ruang antarbutir kelulusan tinggi, akuifer dengan aliran melalui ruang antarbutir kelulusan sedang, dan akuifug setempat berarti. Secara umum pola aliran tanah bebas mengalir relatif dari SSW ke NNE.ABSTRACT. Site evaluation is an important phase of site selection for commercial-scale nuclear power plants (NPP) in Indonesia. Geotechnical and radioactive material dispersion aspects are some of the aspects which are assessed in site evaluation under provisions of laws and regulations. To support those aspect evaluations, it is necessary to conduct hydrogeological characterization in the vicinity of the NPP site. The purpose of this study is to determine the hydrogeological characteristic of the vicinity of the NPP site in Bengkayang Regency, West Kalimantan Province based on geological and geophysical aspects. The methods of this study consist of geomorphological mapping, geological mapping, hydrogeological mapping, geoelectric measurement, and integrated analysis. The study area consists of three morphological units: alluvial plain, isolated hills, and coastal plain. Stratigraphically, the lithology units of the study area, from the oldest to the youngest, consist of andesite, granodiorite, diorite, quartz sand deposits, coastal deposits, and alluvial deposits. The geophysical measurement used is the geoelectric method which is conducted at 12 electrode arrays with 470 m length and spacing of 10 m. In the geoelectrical section, it can be seen that several anomalies can be interpreted as the fractured body of igneous rocks or the diorite intrusion in andesite. These anomaly values are ranged from 300 Wm to >8000 Wm. The relatively low resistivity values (<30 Wm) are interpreted as water saturated-alluvial deposits that could have a thickness of ±100 m. There are three hydrogeological units in the study area: aquifers in which flow is intergranular with high permeability, aquifers in which flow is intergranular with moderate permeability, and aquifug of local importance. Generally, the groundwater in the study area flows from SSW to NNE.

A Modeling Method of the Branch Probability of the Temperature-Induced SGTR Phenomenon

2017 ◽  
Author(s):  
Zibin Liu ◽  
Dingqing Guo ◽  
Bing Zhang ◽  
Jinkai Wang
Keyword(s):  
Steam Generator ◽  
Nuclear Power ◽  
Power Plants ◽  
Modeling Method ◽  
Radioactive Material ◽  
Severe Accident ◽  
Steam Generator Tube ◽  
Modeling Methods ◽  
Radioactive Release ◽  
Level 2

The phenomenon of temperature-induced steam generator tube rupture (TI-SGTR) is a typical phenomenon in the severe accident process of nuclear power plants. The occurrence of the phenomenon may result in the radioactive material bypass the containment, causing a large radioactive release. This paper investigates modeling methods of the phenomenon of temperature-induced SGTR in level 2 PSA and presents an optimizing modeling method to calculate the probability of branching probability of TI-SGTR, aiming at improving the rationality and veracity of level 2 PSA.

Variance of Atmosphere Dispersion Factor for Accident Release from Nuclear Power Plant

2012 ◽  
Vol 518-523 ◽  
pp. 1242-1246 ◽  
Author(s):  
Rui Ping Guo ◽  
Chun Lin Yang
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Probability Distribution ◽  
Wind Direction ◽  
Nuclear Power ◽  
Power Plants ◽  
Atmospheric Dispersion ◽  
Radioactive Material ◽  
The Difference ◽  
Release Height

The growing concern over the effect of atmosphere dispersion resulted from radioactive material was noticeable. This paper demonstrated the variance of atmosphere dispersion factor for accident release from nuclear power plant through running PAVAN (Atmospheric Dispersion of Radioactive Releases from Nuclear Power Plants) model. Also, we investigated the effect of release height (short for H) on atmosphere dispersion factor and compared the correlation between atmosphere dispersion factor and dispersion distance. Our results showed that atmosphere dispersion factor would descend with increased release height. As dispersion distance increasing, the tendency of atmosphere dispersion factor expressed complicated status caused by the difference of wind direction. It was illustrated that the phenomena was caused by the integrated action between the wind direction and release height. The probability distribution of atmosphere dispersion factor also validated that the distribution was depend on the wind direction. Probability analysis indicated that the atmosphere dispersion factor under H=100m was overall less than that under H=75m.

scholarly journals Criminal Liability for Illicit Trafficking of Radioactive Materials

2018 ◽  
pp. 66-70
Author(s):  
O. V. Taran ◽  
O. G. Sandul
Keyword(s):  
Social Relations ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Energy ◽  
Energy Use ◽  
Radiation Safety ◽  
Criminal Liability ◽  
Criminal Code ◽  
Radioactive Material ◽  
Radioactive Materials

The nuclear energy use progressively becomes part of the life of every modern person, who more and more faces radioactive materials in medical institutions, in industry. Half of all electricity generated in Ukraine is generated by nuclear power plants. The peculiarities of the nuclear energy use generate appropriate rules for people dealing with radioactive materials. The article analyzes the standards of the Criminal Code of Ukraine, which provides for liability for acts related to the illegal handling of radioactive materials, for violation of the nuclear and radiation safety rules, violation of radiation safety requirements, the threat of theft of radioactive materials, the illicit manufacturing of a nuclear explosive device, abduction or capture of radioactive materials, attack on radioactive materials transportation means. The grounds and peculiarities for bringing to criminal liability have been reviewed, the range of persons who can be prosecuted has been defined. Conditions and grounds for exemption from criminal liability in the absence of a person's criminal intent to use radioactive material are considered. It has been demonstrated that the Criminal Code of Ukraine, by prohibiting certain actions on the illegal radioactive materials handling, ensures protection of the most important social relations and social benefits.

scholarly journals A Framework for Monitoring and Fault Diagnosis in Nuclear Power Plants Based on Signed Directed Graph Methods

2021 ◽  
Vol 9 ◽  
Author(s):  
Wu Guohua ◽  
Yuan Diping ◽  
Yin Jiyao ◽  
Xiao Yiqing ◽  
Ji Dongxu
Keyword(s):  
Directed Graph ◽  
Process Monitoring ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
High Standard ◽  
Fault Detection And Diagnosis ◽  
Radioactive Material ◽  
Feed Water ◽  
Signed Directed Graph

When nuclear power plants (NPPs) are in a state of failure, they may release radioactive material into the environment. The safety of NPPs must thus be maintained at a high standard. Online monitoring and fault detection and diagnosis (FDD) are important in helping NPP operators understand the state of the system and provide online guidance in a timely manner. Here, to mitigate the shortcomings of process monitoring in NPPs, five-level threshold, qualitative trend analysis (QTA), and signed directed graph (SDG) inference are combined to improve the veracity and sensitivity of process monitoring and FDD. First, a three-level threshold is used for process monitoring to ensure the accuracy of an alarm signal, and candidate faults are determined based on SDG backward inference from the alarm parameters. According to the candidate faults, SDG forward inference is applied to obtain candidate parameters. Second, a five-level threshold and QTA are combined to determine the qualitative trend of candidate parameters to be utilized for FDD. Finally, real faults are identified by SDG forward inference on the basis of alarm parameters and the qualitative trend of candidate parameters. To verify the validity of the method, we have conducted simulation experiments, which comprise loss of coolant accident, steam generator tube rupture, loss of feed water, main steam line break, and station black-out. This case study shows that the proposed method is superior to the conventional SDG method and can diagnose faults more quickly and accurately.

scholarly journals Karakterisasi Geoteknik Fondasi Kandidat Tapak PLTN dengan Metode Seismik Refraksi

EKSPLORIUM ◽  
2021 ◽  
Vol 42 (2) ◽  
pp. 119
Author(s):  
Dwi Haryanto ◽  
Yoshi Rachael ◽  
Dhatu Kamajati ◽  
Gagah Hari Prasetyo ◽  
Heri Syaeful ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Igneous Rock ◽  
Nuclear Power ◽  
Power Plants ◽  
Subsurface Layer ◽  
Seismic Refraction ◽  
Soil Layer ◽  
Geological Mapping ◽  
Rock Layer

ABSTRAK. Pemerintah Indonesia dalam Peraturan Presiden (Perpres) Nomor 38 Tahun 2018 tentang Rencana Induk Riset Nasional Tahun 2017–2045, menetapkan beberapa bidang utama yang akan menjadi prioritas penelitian nasional, salah satunya adalah bidang energi. Dalam tema riset teknologi kelistrikan berbasis energi baru dan terbarukan rendah/nol karbon terdapat topik riset teknologi Pembangkit Listrik Tenaga Nuklir (PLTN) skala komersial. Pada topik riset tersebut, ditetapkan bahwa dalam jangka waktu penelitian tahun 2020–2024, dihasilkan purwarupa PLTN. Pada penelitian ini, karakterisasi geoteknik tapak PLTN dilakukan dengan menggunakan metode seismik refraksi guna melengkapi data penelitian sebelumnya. Tujuan penelitian ini adalah untuk mengetahui profil perlapisan batuan bawah permukaan untuk estimasi pekerjaan terkait fondasi PLTN. Pemetaan geologi dan akuisisi data geofisika, pengolahan, serta interpretasi tanah/batuan berdasarkan parameter kecepatan gelombang kompresi (Vp). Hasil pemetaan geologi menunjukkan adanya 2 satuan batuan beku yaitu diorit kuarsa dan andesit. Hasil pengolahan dan interpretasi data seismik refraksi menghasilkan model penampang Vp pada lapisan batuan bawah permukaan. Terdapat 3 lapisan batuan di lokasi penelitian yaitu lapisan tanah (Vp = 361–715 m/s), lapisan batuan beku lapuk (Vp = 1.386–2.397 m/s), dan lapisan beku segar (Vp = 3.789–6.133 m/s). Perkiraan densitas batuan beku segar berdasarkan perhitungan adalah 2,43–2,74 g/cm3. Hasil pemodelan dapat menunjukkan kedalaman dan struktur bawah permukaan lapisan batuan beku segar yang dapat menjadi fondasi bangunan PLTN.ABSTRACT. Presidential Regulation (Perpres) number 38 of 2018 concerning the National Research Master Plan for 2017–2045, the Government of Indonesia establishes several main areas that will become national research priorities, one of which is the energy sector. In the research theme of electricity technology based on new and renewable low/zero carbon energy, there is the topic of research on commercial-scale Nuclear Power Plant (NPP) technology. On the research topic, it was determined that within the research period of 2020–2024, a prototype nuclear power plant would be produced. Research related to the geotechnical characterization of the nuclear power plant site using the seismic refraction method was carried out to complement the previous research data. The purpose of this study was to determine the subsurface rock layer profile for estimation of work related to nuclear power plant foundations. Geological mapping and geophysical data acquisition, processing, as well as soil/rock interpretation based on the compression wave velocity (Vp) parameter are carried out to achieve this goal. The results of geological mapping show that there are 2 igneous rock units, namely quartz diorite and andesite. The results of processing and interpreting seismic refraction data produced a cross-sectional model of Vp in the subsurface rock layers. There are 3 rock layers in the research location, namely soil layer (Vp = 361–715 m/s), weathered igneous rock layer (Vp = 1.386–2,396 m/s), and fresh igneous layer (Vp = 3.789–6.133 m/s). The estimated density of fresh igneous rock based on calculations is 2.43–2.74 g/cm3. The modeling results can show the depth and structure of the subsurface layer of fresh igneous rock that can be the foundation of nuclear power plants.

scholarly journals Hypothetical Accident in Polish Nuclear Power Plant. Worst Case Scenario for Main Polish Cities

2019 ◽  
Vol 26 (1) ◽  
pp. 9-28
Author(s):  
Andrzej Mazur
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Atmospheric Transport ◽  
Radioactive Material ◽  
Second Phase ◽  
Pollution Transport ◽  
Worst Case ◽  
Hypothetical Accident

Abstract Poland is under threat of potential accidents in nuclear power plants located in its close vicinity, in almost all neighboring countries. Moreover, there are plans to establish a new nuclear power plant in Polish coast. In this paper the analysis of atmospheric transport of radioactive material released during a potential accident in the future nuclear power plant is presented. In the first part of study transport of radioactivity as seen from the long time perspective is analyzed. This involves trajectory analysis as a tool for describing the statistics of air pollution transport pattern and screening the meteorological situations for episode studies. Large sets of meteorological data for selected episodes were stored as a result of this process. Estimation of risk includes both analysis of the consequences and probability analysis of an occurrence of such situation. Episodes then were comprehensively studied in the second phase of the study, using the Eulerian dispersion model for simulation of atmospheric transport of pollutants. This study has proven that the time needed for reaction in case of (hypothetical) accident is enormously short.

On-Site Evaluation of Bending Stresses at the Root of Small Bore Pipes by Accelerometric Measurements

2003 ◽  
Author(s):  
J. Guillou ◽  
L. Paulhiac
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Numerical Models ◽  
Operating Conditions ◽  
Strain Gauges ◽  
Bending Stress ◽  
Piping Systems ◽  
Bending Stresses ◽  
Site Evaluation

Several vibration-induced failures at the root of small bore piping systems occurred in French nuclear power plants in past years. The evaluation of the failure risk of the small bore pipes requires a fair estimation of the bending stress under operating conditions. As the use of strain gauges is too time-consuming in the environmental conditions of nuclear power plants, on-site acceleration measurements combined with numerical models are easier to handle. It still requires yet a large amount of updating work to estimate the stress in multi-span pipes with elbows and supports. The aim of the present study is to propose an alternate approach using two accelerometers to measure the local nozzle deflection, and an analytical expression of the bending stiffness of the nozzle on the main pipe. A first formulation is based on a static deformation assumption, thus allowing the use of a simple analog converter to get an estimation of the RMS value of the bending stress. To get more accurate results, a second method is based on an Euler Bernoulli deformation assumption: a spectral analyzer is then required to get an estimation of the spectrum of the bending stress. A better estimation of its RMS value is then obtained. An experimental validation of the methods based on strain gauges has been successfully performed.

Incorporation of the Radioactive Interinfluence in Multi-Unit Seismic PRA

2018 ◽  
Author(s):  
Shuhei Matsunaka ◽  
Chikahiro Sato ◽  
Manabu Watanabe
Keyword(s):  
Nuclear Power Station ◽  
Nuclear Power ◽  
Power Plants ◽  
Evaluation Method ◽  
Common Factor ◽  
Radioactive Material ◽  
Power Station ◽  
Core Damage ◽  
Accident Management ◽  
Multiple Units

Kashiwazaki-Kariwa nuclear power station of TEPCO is the largest nuclear power station in the world, and it has seven nuclear power plants. As the experience at Fukushima Daiichi nuclear power station accident in March 2011 involving concurrent core damage at multiple units, it is considered that the risk derived from hazards of Earthquakes and Tsunamis is relatively significant in Japan, and these events have a high likelihood of damaging multiple units simultaneously. Therefore, it is very important to grasp the multi-unit specific risk. Although there are some unique accident scenarios of Multi-Unit PRA, this paper focuses on the influence of radioactive materials released outside the containment vessel on the accident management of the adjacent unit. The events including core damage and loss of containment function should be considered as the causes of the release of radioactive substances, and operator’s operation or the like should be considered as objects to be adversely affected by them. It is necessary to incorporate that into PRA to confirm the effect on risk. It is very difficult in terms of the maturity of evaluation method and the calculation load to accurately incorporate consequences derived from time series of various events and complicated interaction into PRA model. Therefore, as the first step in evaluating the risk of influence of radioactive material release on the accident management, some streamlining efforts are implemented according to the purpose. For example, Kashiwazaki-Kariwa unit 6 and unit 7 were set as the target units for model simplification. We also assume the earthquake as the initiating event due to the strong common factor for multi units. Whether or not to be operable in the adjacent plant is set conservatively based on deterministic evaluation. PRA taking into consideration the radiation influence by multi-unit accident is compared with normal PRA. Some kind of Core Damage Frequency (CDF) such as CDF1 (Core Damage Frequency at which the damage of one or the other of two unit occur), CDF2 (CDF at which the damage of both of units occur) and CDFTOTAL (CDF at which the damage of one or more units occur: CDF1 + CDF2) are quantified, and the degree of this issue is provided. Although the change of CDFTOTAL was insignificant, the necessity of further study was shown from the viewpoint of the amount and timing of radioactive substance released due to an approximately 1.5-fold increase in CDF2.

scholarly journals The ability to use FLEXPART in simulation of the long-range radioactive materials dispersed from nuclear power plants near Vietnam border

2016 ◽  
Vol 6 (4) ◽  
pp. 40-48
Author(s):  
Kim Long Pham ◽  
Hao Quang Nguyen ◽  
Duy Hien Pham ◽  
Xuan Anh Do ◽  
Duc Thang Duong ◽  
...  
Keyword(s):  
Long Range ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Dispersion Model ◽  
Meteorological Data ◽  
Transport Processes ◽  
Radioactive Material ◽  
Radioactive Materials ◽  
The Impact

FLEXPART is a Lagrangian transport and dispersion model suitable for the simulation of a large range of atmospheric transport processes. FLEXPART has been researched and applied   in simulation of the long-range dispersion of radioactive materials. It can be applicable to the problem of radioactive materials released from the nuclear power plants impact on Vietnam. This report presents simulation of radioactive dispersion from the accident assumed Fangchenggang and Changjiang nuclear power plants in China with the FLEXPART, using meteorological data from the National Centers for Environmental Prediction (NCEP). The results of simulations and analyzing showed good applicability of FLEXPART for a long-range radioactive materials dispersion. The preliminary simulation results show that the impact of the radioactive material dispersion in Vietnam varies by the well-known characteristics of the monsoon of our country. Winter is the time when the dominant northeast winds up radioactive dispersion most towards our country, its sphere of influence extends from the Northeast (Quang Ninh) to North Central (Da Nang).

Pacific Solidarity and Atomic Aggression

2017 ◽  
Author(s):  
Simon Avenell
Keyword(s):  
Pacific Ocean ◽  
Radioactive Waste ◽  
Industrial Pollution ◽  
Nuclear Power ◽  
Power Plants ◽  
Radioactive Material ◽  
Mariana Trench ◽  
The Pacific ◽  
The Pacific Ocean ◽  
Ocean Dumping

This chapter traces the emergence and evolution of a transnational movement opposing the planned dumping of Japanese radioactive waste material in the Pacific Ocean near the Mariana Trench. With its growing stockpile of radioactive waste from nuclear power plants, in the 1970s Japanese officials hatched plans to dump radioactive material in steel canisters in the Pacific. In response, activists on islands in Micronesia mobilized in staunch opposition in the late 1970s. They were joined by Japanese antinuclear groups who brought Pacific activists to Japan to give speeches and lobby officials. The chapter explores how this transnational struggle was able to force a postponement and ultimately the abandonment of the ocean dumping plan. As with movements opposing industrial pollution export in the 1970s, this mobilization opened Japanese activists’ eyes to the nuclear victimization of Pacific peoples and, in turn, forced a reconsideration of Japan as the only victim of radiation worldwide.

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