scholarly journals ANALISIS KELAYAKAN FINANSIAL PROYEK PLTN SMR DI INDONESIA DENGAN MEMPERTIMBANGKAN VARIABEL KETIDAKPASTIAN

2015 ◽  
Vol 17 (2) ◽  
pp. 133
Author(s):  
Nuryanti Nuryanti ◽  
Suparman Suparman ◽  
Mochamad Nasrullah ◽  
Elok S. Amitayani ◽  
Wiku Lulus Widodo
Keyword(s):  
Monte Carlo ◽  
Power Plant ◽  
Nuclear Power ◽  
Inflation Rate ◽  
Probabilistic Approach ◽  
Selling Price ◽  
Average Value ◽  
Financial Feasibility ◽  
The Relationship ◽  
Capital Intensive

ABSTRAK ANALISIS KELAYAKAN FINANSIAL PROYEK PLTN SMR DI INDONESIA DENGAN MEMPERTIMBANGKAN VARIABEL KETIDAKPASTIAN. SMR merupakan salah satu alternatif mengatasi ketergantungan wilayah Luar Jawa Bali terhadap PLTD. Masalah yang sangat krusial dalam proyek PLTN (termasuk SMR) adalah finansial, terkait dengan sifat padat modal pada proyek ini. Selain itu, pada proyek PLTN SMR juga dimungkinkan terjadinya beberapa variabel ketidakpastian. Penelitian ini bertujuan untuk melakukan analisis kelayakan finansial proyek PLTN SMR dengan mengakomodasi kemungkinan terjadinya variabel ketidakpastian tersebut. Metodologi yang digunakan adalah analisis probabilistik yang dilakukan dengan teknik Monte Carlo. Teknik ini mensimulasikan keterkaitan antara variabel-variabel ketidakpastian dengan indikator kelayakan finansial proyek. Hasil penelitian menunjukkan bahwa pada pendekatan probabilistik proyek PLTN SMR dinilai layak pada “most probable value” harga jual listrik sebesar 15 cents/kWh, ditunjukkan dengan rata-rata NPV yang positif (US$ 135.324.004) dan rata-rata kedua nilai IRR yang lebih dari MARR (IRR proyek = 10,65%, IRR Equity = 14,29%, sementara MARR = 10%). Probabilitas ditolaknya proyek PLTN SMR adalah sekitar 20%. Tiga variabel utama yang paling berpengaruh dalam proyek adalah: harga jual listrik, biaya investasi dan tingkat inflasi. Kata kunci: kelayakan finansial, PLTN SMR, variabel ketidakpastian, NPV, IRR ABSTRACT FINANCIAL FEASIBILITY ANALYSIS ON SMALL MEDIUM REACTOR NUCLEAR POWER PLANT (SMR NPP) PROJECT IN INDONESIA UNDER UNCERTAINTY. NPP SMR is one alternative to overcome the Outside Java Bali region's dependence on diesel power plant. One crucial issue in the NPP project (including SMR) would be financing, associated with the capital-intensive nature of the project. In addition, the SMR NPP project also be vulnerable in occurrence of some uncertainties. Therefore, this study aimed to analyze the financial feasibility of SMR NPP project by accomadating the possibility of the uncertainties. The methodology used is probabilistic analysis which was performed by Monte Carlo technique. This technique simulates the relationship between the uncertainty variables with financial feasibility indicators. The results showed that in probabilistic approach, SMR NPP project is considered feasible on the "most probable value" of electricity selling price of 15 cents/kWh, indicated by positive average value of NPV (US$ 135,324,004) and the average value of both of IRRs are bigger than MARR (IRR project = 10.65%, IRR Equity = 14.29%, while MARR = 10%). The probability of rejection of the SMR project was about 20%. The three main variables that are most influential in the project were: selling price of electricity, invesment cost and inflation rate. Keywords: financial feasibility, SMR  NPP, uncertainties, NPV, IRR

scholarly journals INVESTIGATION OF RELATIONSHIP BETWEEN PINE (PINUS SYLVESTRIS L.) BIOMASS AND 137CS SPECIFIC ACTIVITY IN WOOD

2006 ◽  
Vol 14 (3) ◽  
pp. 135-140 ◽  
Author(s):  
Donatas Butkus ◽  
Ingrida Pliopaitė Bataitienė
Keyword(s):  
Power Plant ◽  
Pinus Sylvestris ◽  
Nuclear Power ◽  
Specific Activity ◽  
Chernobyl Nuclear Power Plant ◽  
Biomass Growth ◽  
Annual Rings ◽  
Global Pollution ◽  
Nuclear Explosions ◽  
Average Value

The paper analyses relationship between pine (Pinus sylvestris L.) biomass and the specific activity of an artificial radio‐isotope 137Cs in wood. The specific activity of 137Cs was measured in the segments of pine (Pinus sylvestris L.) annual rings. The biomass of segments and the density of wood were estimated experimentally. It is determined that relationship between pine (Pinus sylvestris L.) biomass and pine age is not linear. In the variation of biomass are time when biomass grows slowly (25–55 pine age or 1959–1990 m. period). The specific activity of 137Cs in pine annual rings depends on the rapidity of biomass growth. The specific activity of 137Cs varied from 0,3 ± 0,1 to 13,4 ± 2,7 Bq/kg when the biomass grew rapidly and its average value was 4,3±1,1 Bq/kg. When the biomass grew slowly, the specific activity of 137Cs varied from 1,8 ± 0,7 to 20,6 ± 5,3 Bq/kg, and its average value was 9,6 ± 2,6 Bq/kg. Global pollution after nuclear explosions, pollution after the Chernobyl Nuclear Power Plant accident and uptake of 137Cs from roots had an influence on the specific activity of 137Cs in pine annual rings.

Nonlinear Probabilistic Analysis of the Failure Pressure of NPP Shielding Plate

2016 ◽  
Vol 837 ◽  
pp. 214-221
Author(s):  
Juraj Kralik ◽  
Juraj Kralik Jr. ◽  
Maros Klabnik ◽  
Alzbeta Grmanova
Keyword(s):  
Monte Carlo ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Probabilistic Analysis ◽  
Nuclear Power ◽  
Safety Assessment ◽  
Fragility Curve ◽  
Failure Pressure ◽  
Surface Method ◽  
Central Composite

This paper describes the nonlinear probabilistic analysis of the failure pressure of the shielding plate of the reactor box of the nuclear power plant under a high internal overpressure and temperature. The scenario of the hard accident in Nuclear power plant (NPP) and the methodology of the calculation of the fragility curve of the failure overpressure using the probabilistic safety assessment PSA 2 level is presented. The fragility curve of the failure pressure was determined using 45 probabilistic simulations using the response surface method (RSM) with the Central Composite Design (CCD) for 106 Monte Carlo simulations for each model and 5 level of the overpressure.

SIMULATION OF THE RESPONSE OF A LaBr3(Ce) DETECTOR IN AN ATMOSPHERE CONTAMINATED WITH RADIONUCLIDES AFTER A NUCLEAR POWER PLANT ACCIDENT

2019 ◽  
Vol 186 (2-3) ◽  
pp. 346-350
Author(s):  
Tomáš Urban ◽  
Petr Vágner
Keyword(s):  
Monte Carlo Simulation ◽  
Monte Carlo ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Monitoring Network ◽  
Scintillation Detectors ◽  
Scintillation Crystal ◽  
Probe Response

Abstract The aim of this paper is to investigate the possibility of using detectors based on LaBr3(Ce) scintillation crystal as part of gamma spectrometry systems for field use and possibly as part of a monitoring network around nuclear power plants, i.e. whether LaBr3(Ce) detectors can follow the classical scintillation detectors based on NaI (Tl). For this purpose, the Monte Carlo simulation of the IPROL-1 probe response was performed in the simplified geometry of the radionuclides-contaminated atmosphere. A study shows that a LaBr3(Ce)-based probe is usable for this purpose and results are at least comparable to those with a conventional NaI (Tl)-based probe.

scholarly journals Measurement of anthropogenic radionuclides in post-Fukushima Pacific seawater samples

Nukleonika ◽  
2015 ◽  
Vol 60 (3) ◽  
pp. 545-550 ◽  
Author(s):  
Guillaume Lutter ◽  
Faidra Tzika ◽  
Mikael Hult ◽  
Michio Aoyama ◽  
Yasunori Hamajima ◽  
...  
Keyword(s):  
Monte Carlo ◽  
Power Plant ◽  
North Pacific ◽  
Nuclear Power ◽  
Gamma Ray ◽  
Gamma Ray Spectrometry ◽  
Anthropogenic Radionuclides ◽  
Vast Number ◽  
Hpge Detectors ◽  
Seawater Samples

Abstract Following the accident at the Daiichi Fukushima nuclear power plant in 2011, a vast number of Pacific seawater samples from many locations far from Fukushima have been collected by Japanese investigators. Due to dilution, the activities of radionuclides from North Pacific seawater samples are very low, which calls for extraordinary measures when being measured. This study focuses on the metrological aspects of the gamma-ray spectrometry measurements performed on such samples in two underground laboratories; at HADES (by JRC-IRMM in Belgium), and at Ogoya (by Kanazawa University in Japan). Due to many samples and long measurement times, all available HPGe detectors needed to be employed. In addition to single coaxial detectors, this involved multidetector systems and well detectors. Optimization of detection limits for different radionuclides and detectors was performed using Monte Carlo simulations.

Anti-Ratcheting Design Software for Primary Auxiliary Pipeline in Nuclear Power Plant

2010 ◽  
Vol 118-120 ◽  
pp. 126-130
Author(s):  
Zhe Guang Zhang ◽  
Xu Chen ◽  
Fei Xue ◽  
Wei Wei Yu
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Display Module ◽  
Ansys Simulation ◽  
Asme Code ◽  
Computing Module ◽  
The Relationship

In this study, based on ASME Code Section III, France RCC-MR, ANSYS simulation and experimental data, ratcheting and ratcheting boundary are obtained to determine allowed loading of primary auxiliary pipeline in nuclear power plant. A software of pressurized water reactor auxiliary pipeline anti-ratcheting design is compiled. The calculation method to determine the boundary of ratcheting effect is proposed in order to provide a basis for pipe structural design. This work focuses on the work of the establishment of the structure of software system. The structure mainly composed by three program modules, i.e. the database module, data computing module and data display module. The function of each module and the relationship between the modules are explained. An example to determine ratcheting boundary is presented in the paper.

scholarly journals Soil radioactivity and elemental characterization of area proposed for the first nuclear power plant at Red Sea state, eastern Sudan

2020 ◽  
Vol 5 (3) ◽  
Author(s):  
Nessreen Abdelfatah Ali Abdoun
Keyword(s):  
Power Plant ◽  
Nuclear Power ◽  
Gamma Ray ◽  
Absorbed Dose ◽  
Dose Rates ◽  
Average Value ◽  
Gamma Ray Spectrometer ◽  
Gamma Index ◽  
Radium Equivalent ◽  
Low Levels

Abstract  This work was carried out with the aim to establish baseline data of soil radioactivity prior commissioning the first nuclear power plant for electricity production in the Sudan. A total of 105 soil samples from the proposed area were collected and analyzed using Gamma-ray spectrometer, X-ray Fluorescence and Atomic Absorption. Ambient dose rates were measured during sampling using radiation survey meters. Based on radionuclides in soil; some radiological hazard indices (such as absorbed dose rates, Radium-Equivalent Activity, External Hazard, and Gamma index) were computed. The results exhibit that226Ra, 232Th,40Kand 137Cs concentration ranged from0.55-88.9, 1.63-76.6, 24-1100 and 0.001-1.03 Bq/kg with an average value of10.43, 11.12, 361.2and 0.045Bq/kg respectively. The average value of absorbed dose rate(29.92nGy/h), Radium equivalent (70.55 Bq/Kg), external hazard (0.19), Gamma index. (0.25) and those parameters are lower than the corresponding global average. The results of the study revealed that the average values of 226Ra, 232Th, 40K and 137Cs fall within the global average value. GIS Predictive exhibited the spatial distribution of radioactivity trends with low levels at eastern part towards the Red Sea while high values observed at the desert (western part). This trend in addition to low levels has a very good impact to decision makers for consideration in site selection of NPP. Pearson correlation coefficient shows a correlation between the variables 226Ra and 232Th (0.69); Cr and Au (0.82); Br and Nb (0.84),Hf and Sb (+0.75) with no significant correlations between radioactive and radioactive elements. Keywords: Road map, GIS, Gamma-ray Spectrometer, Effective dose.  

Root Cause Evaluation on Suction Piping Vibration of Auxiliary Feedwater Pump

2004 ◽  
Author(s):  
Chang-Bin Jeon ◽  
Byoung-Hwa Choi ◽  
Mun-Baek Park
Keyword(s):  
Power Plant ◽  
Nuclear Power ◽  
Low Flow ◽  
Pulsation Frequency ◽  
Root Cause ◽  
Feedwater Pump ◽  
Operational Test ◽  
Closed Position ◽  
Suction Line ◽  
The Relationship

Abnormal vibration was observed in the suction piping of Auxiliary Feedwater (AF) pump during a pre-operational test at an operating nuclear power plant in Korea. The vibration and noise were initiated when a recirculation valve located downstream of the pump was gradually closed to about 80%. The vibration reached its peak when the recirculation valve was in a fully closed position. After the test, it was found that the bearing of AF pump was damaged. The vibration of suction line was measured during a retest and the cause of vibration was evaluated. This paper presents a root cause of the vibration problem experienced in the pump suction piping. It also reviews the relationship between the vibration of suction piping and minimum flow operations. In conclusion, the pulsation frequency generated from the pump internal during a low flow operation of the pump caused the suction piping vibration.

Mathematical Modeling for Contingency Determination for Nuclear Power Plant Construction Projects

2014 ◽  
Author(s):  
Wei Zhao ◽  
Shenjun Xu
Keyword(s):  
Monte Carlo Simulation ◽  
Risk Management ◽  
Monte Carlo ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Construction Projects ◽  
Nuclear Power ◽  
Historical Data ◽  
Plant Construction ◽  
Lump Sum

This paper uses the China AP1000 project as an example to exhibit the application of quantitative risk management in nuclear power plant construction projects. For those lump sum contracts, one of the most significant purposes of quantitative risk management is to determine the contingency, i.e. the reserved money and time for projects. This paper studies the application of Monte Carlo simulation in determining the contingency, taking into account the distinctive features of nuclear power projects. Most nuclear power projects, especially advanced ones such as Generation III and above, meet one common obstacle in estimating key economic indicators — the absence of historical data due to its avant-garde design. As cost estimators of the coal power plant contractors may collect their data from thousands of previous cases, nuclear power plant contractors, especially in many developing countries, do not have a shared database of financial data. Some first-of-a-kind nuclear power plants have absolutely no historical data to look up. This paper aims to provide a resolution to this problem. First, the feasibility and representativeness of different probability distributions are compared based on their respective skewness and kurtosis to determine the best-suited distribution in nuclear power projects. This paper also analyzes the use of second-order Monte Carlo simulation in reducing the error caused by the biased estimation of inexperienced risk assessment engineers.

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