• Title/Summary/Keyword: Code calibration

Search Result 125, Processing Time 0.023 seconds

Experimental and Simulated Efficiency of a HPGe Detector in the Energy Range of $0.06{\sim}11$ MeV

  • Park Chang Su;Sun Gwang Min;Choi H.D.
    • Nuclear Engineering and Technology
    • /
    • v.35 no.3
    • /
    • pp.234-242
    • /
    • 2003
  • The full energy peak efficiency of a hyper pure germanium (HPGe) detector was calibrated in a wide energy range from 0.06 to 11 MeV. Both the experimental technique and the Monte Carlo method were used for the efficiency calibration. The measurement was performed using the standard radioisotopes in the low energy region of $60{\sim}1408$ keV, which was further extended up to 11 MeV by using the $^{14}N(n,r)\;and\;^{35}Cl(n,r)$ reactions. The GEANT Monte Carlo code was used for efficiency calculation. The calculated efficiency had the same dependency on the r-ray energy with the measurement, and the discrepancy between the calculation and the measurement was minimized by fine-tuning of the detector geometry. From the calculated result, the efficiency curve of the HPGe detector was reliably determined particularly in the high energy region above several MeV, where the number of measured efficiency points is relatively small despite the wide energy region. The calculated efficiency agreed with the measurement within about $7\%$. In addition to the efficiency calculation, the origin of the local minimum near 600 keV on the efficiency curve was analyzed as a general characteristics of a HPGe detector.

The effect of front edge on efficiency for point and volume source geometries in p-type HPGe detectors

  • Esra Uyar ;Mustafa Hicabi Bolukdemir
    • Nuclear Engineering and Technology
    • /
    • v.54 no.11
    • /
    • pp.4220-4225
    • /
    • 2022
  • Monte Carlo (MC) simulations are increasingly being used as an alternative or supplement to the gamma spectrometric method in determining the full energy peak efficiency (FEPE) necessary for radionuclide identification and quantification. The MC method is more advantageous than the experimental method in terms of both cost and time. Experimental calibration with standard sources is difficult, especially for specimens with unusually shaped geometries. However, with MC, efficiency values can be obtained by modeling the geometry as desired without using any calibration source. Modeling the detector with the correct parameters is critical in the MC method. These parameters given to the user by the manufacturer are especially the dimensions of the crystal and its front edge, the thickness of the dead layer, dimensions, and materials of the detector components. This study aimed to investigate the effect of the front edge geometry of the detector crystal on efficiency, so the effect of rounded and sharp modeled front edges on the FEPE was investigated for <300 keV with three different HPGe detectors in point and volume source geometries using PHITS MC code. All results showed that the crystal should be modeled as a rounded edge, especially for gamma-ray energies below 100 keV.

Probability-Based WSD Code for Reinforced Concrete (확률이론(確率理論)에 기초(基礎)한 철근(鐵筋)콘크리트 허용응력설계규준(許容應力設計規準))

  • Cho, Ryo Nam;Shin, Jae Chul;Chun, Chai Myung
    • KSCE Journal of Civil and Environmental Engineering Research
    • /
    • v.6 no.4
    • /
    • pp.61-68
    • /
    • 1986
  • This paper presents a method for developing a probability-based working stress design code for reinforced concrete. Reliability of reinforced concrete structural members is evaluated by using an advanced second moment reliability method, and then, a practical method for code calibration is shown in this paper. The target reliability indices for various structural elements are determined by considering the results of the numerical studies on the safety of the structures designed by the current code, and by reflecting the construction practice. A set of allowable stresses and safety factors for reinforced concrete is proposed as a possible substitute for the current safety provisions, based on the rational target reliability indices.

  • PDF

Operational Water Quality Forecast for the Yeongsan River Using EFDC Model (EFDC 수질모델을 이용한 영산강 수계 수질 예측)

  • Shin, Chang Min;Min, Joong-Hyuk;Park, Su Young;Choi, Jungkyu;Park, Jong Hwan;Song, Young Sik;Kim, Kyunghyun
    • Journal of Korean Society on Water Environment
    • /
    • v.33 no.2
    • /
    • pp.219-229
    • /
    • 2017
  • A watershed-river linked modeling system was developed to forecast the water quality, particularly weekly changes in chlorophyll-a concentration, of the Yeongsan River, Korea. Hydrological Simulation Program-Fortran (HSPF) and Environmental Fluid Dynamics Code (EFDC) were adopted as the basic model framework. In this study, the EFDC model was modified to effectively simulate the operational condition and flow of multi-functional weirs constructed in the main channel of rivers. The model was tested against hydrologic, water quality and algal data collected at the right upstream sites of two weirs in 2014. The mean absolute errors (MAEs) of the model calibration on the annual variations of river stage, TN, TP, and algal concentration are 0.03 ~ 0.10 m, 0.65 ~ 0.67 mg/L, 0.03 ~ 0.04 mg/L, and $9.7{\sim}10.8mg/m^3$, respectively. On the other hand, the MAE values of forecasting results for chlorophyll-a level at the same sites in 2015 range from 18.7 to $22.4mg/m^3$, which are higher than those of model calibration. The increased errors in forecasting are mainly attributed to the higher uncertainties of weather forecasting data compared to the observed data used in model calibration.

A study on slim-hole neutron logging based on numerical simulation (소구경 시추공에서의 중성자검층 수치모델링 연구)

  • Ku, Bonjin;Nam, Myung Jin
    • Geophysics and Geophysical Exploration
    • /
    • v.15 no.4
    • /
    • pp.219-226
    • /
    • 2012
  • This study provides an analysis on results of neutron logging for various borehole environments through numerical simulation based on a Monte Carlo N-Particle (MCNP) code developed and maintained by Los Alamos National Laboratory. MCNP is suitable for the simulation of neutron logging since the algorithm can simulate transport of nuclear particles in three-dimensional geometry. Rather than simulating a specific tool of a particular service company between many commercial neutron tools, we have constructed a generic thermal neutron tool characterizing commercial tools. This study makes calibration chart of the neutron logging tool for materials (e.g., limestone, sandstone and dolomite) with various porosities. Further, we provides correction charts for the generic neutron logging tool to analyze responses of the tool under various borehole conditions by considering brine-filled borehole fluid and void water, and presence of borehole fluid.

Influence of infill panels on an irregular RC building designed according to seismic codes

  • Ercolino, Marianna;Ricci, Paolo;Magliulo, Gennaro;Verderame, Gerardo M.
    • Earthquakes and Structures
    • /
    • v.10 no.2
    • /
    • pp.261-291
    • /
    • 2016
  • This paper deals with the seismic assessment of a real RC frame building located in Italy, designed according to the current Italian seismic code. The first part of the paper deals with the calibration of the structural model of the investigated building. The results of an in-situ dynamic identification test are employed in a sensitivity and parametric study in order to find the best fit model in terms of frequencies and modal shapes. In the second part, the safety of the structure is evaluated by means of nonlinear static analyses, taking into account the results of the previous dynamic study. In order to investigate the influence of the infills on the seismic response of the structure, the nonlinear static analyses are performed both neglecting and taking into account the infill panels. The infill panels differently change the behavior of the structure in terms of strength and stiffness at different seismic intensity levels. The assessment study also verifies the absence of brittle failures in structural elements, which could be caused by either the local interaction with infills or the failure of the strength hierarchy.

Effect of normal load on the crack propagation from pre-existing joints using Particle Flow Code (PFC)

  • Haeri, Hadi;Sarfarazi, Vahab;Zhu, Zheming
    • Computers and Concrete
    • /
    • v.19 no.1
    • /
    • pp.99-110
    • /
    • 2017
  • In this paper, the effect of normal load on the failure mechanism of echelon joint has been studied using PFC2D. In the first step, calibration of PFC was undertaken with respect to the data obtained from experimental laboratory tests. Then, six different models consisting various echelon joint were prepared and tested under two low and high normal loads. Furthermore, validation of the simulated models were cross checked with the results of direct shear tests performed on non-persistent jointed physical models. The simulations demonstrated that failure patterns were mostly influenced by normal loading, while the shear strength was linked to failure mechanism. When ligament angle is less than $90^{\circ}$, the stable crack growth length is increased by increasing the normal loading. In this condition, fish eyes failure pattern occur in rock bridge. With higher ligament angles, the rock bridge was broken under high normal loading. Applying higher normal loading increases the number of fracture sets while dilation angle and mean orientations of fracture sets with respect to ligament direction will be decreased.

Numerical simulation of tensile failure of concrete using Particle Flow Code (PFC)

  • Haeri, Hadi;Sarfarazi, Vahab
    • Computers and Concrete
    • /
    • v.18 no.1
    • /
    • pp.39-51
    • /
    • 2016
  • This paper considers the tensile strength of concrete samples in direct, CTT, modified tension, splitting and ring tests using both of the experimental tests and numerical simulation (particle flow code 2D). It determined that which one of indirect tensile strength is close to direct tensile strength. Initially calibration of PFC was undertaken with respect to the data obtained from Brazilian laboratory tests to ensure the conformity of the simulated numerical models response. Furthermore, validation of the simulated models in four introduced tests was also cross checked with the results from experimental tests. By using numerical testing, the failure process was visually observed and failure patterns were watched to be reasonable in accordance with experimental results. Discrete element simulations demonstrated that the macro fractures in models are caused by microscopic tensile breakages on large numbers of bonded discs. Tensile strength of concrete in direct test was less than other tests results. Tensile strength resulted from modified tension test was close to direct test results. So modified tension test can be a proper test for determination of tensile strength of concrete in absence of direct test. Other advantages shown by modified tension tests are: (1) sample preparation is easy and (2) the use of a simple conventional compression press controlled by displacement compared with complicate device in other tests.

DC-DC Boost Converter using Offset-Controlled Zero Current Sensor for Low Loss Thermoelectric Energy Harvesting Circuit (저 손실 열전변환 하베스팅을 위해 제로전류센서의 오프셋을 조절하는 부스트 컨버터)

  • Joo, Sunghwan;Kim, Kiryong;Jung, Dong-Hoon;Jung, Seong-Ook
    • Journal of IKEEE
    • /
    • v.20 no.4
    • /
    • pp.373-377
    • /
    • 2016
  • This paper presents a low power boost converter using offset controlled Zero Current Sensor (ZCS) control for thermoelectric energy harvesting.[1] [5] Offset controlled ZCS uses adjustable pre-offset that is controled by 6bit code each connected gate of NMOS for switching. Offset controlled ZCS demonstrates an efficiency that is higher than using analog comparator ZCS and that is smaller area than using delay line ZCS. Experimentally, the offset controlled ZCS system consumes 10 times less power than analog comparator ZCS based system at similar performance.

Uranium Enrichment Determination Using a New Analysis Code for the U XKα Region: HyperGam-U

  • Kim, Junhyuck;Choi, Hee-Dong;Park, Jongho
    • Nuclear Engineering and Technology
    • /
    • v.48 no.3
    • /
    • pp.778-784
    • /
    • 2016
  • HyperGam-U was recently developed to determine uranium enrichment based on ${\gamma}$- and X-ray spectroscopy analysis. The $XK_{\alpha}$ region of the uranium spectrum contains 13 peaks for $^{235}U$ and $^{238}U$ and is used mainly for analysis. To describe the X-ray peaks, a Lorentzian broadened shape function was used, and methods were developed to reduce the number of fitting parameters for decomposing the strongly overlapping peaks using channel-energy, energy-width, and energy-efficiency calibration functions. For validation, eight certified reference material uranium samples covering uranium enrichments from 1% to 99% were measured using a high-resolution planar high-purity germanium detector and analyzed using the HyperGam-U code. When corrections for the attenuation and true coincidence summing were performed for the detection geometry in this experiment, the goodness of fit was improved by a few percent. The enrichment bias in this study did not exceed 2% compared with the certified values for all measured samples.