• Title/Summary/Keyword: Atomic parameters

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The Effect of Processing Parameters on the Deposition Behavior of a Spent Fuel Surrogate in the Molten Salt Electrorefining

  • Lee, Jong-Hyeon;Kang, Young-Ho;Hwang, Sung-Chan;Kim, Eung-Ho;Yoo, Jae-Hyung
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2004.06a
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    • pp.319-329
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    • 2004
  • The electrorefining experiments with an anode composed of U, Y, Gd, Nd and Ce (or U, Gd, Dy and Ce) were carried out in the KC1-LiCl eutectic melt at $500^{\circ}C$, Uranium was the major component in the cathode deposits at the high initial uranium concentration, and the separation factors of the uranium with respect to the rare earths (REs) were calculated according to the applied voltage and the uranium concentration in the molten salt. The current efficiency was inversely in proportion to the applied voltage in the range of 1.0 V to 1, 9 V (vs. STS304L). The dependency of the applied voltage on the current efficiency as well as the deposition rate was discussed in terms of the microstructural feature and crystal structure of the deposit.

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Application of Self-Organizing Fuzzy Logic Controller to Nuclear Steam Generator Level Control

  • Park, Gee-Yong;Park, Jae-Chang;Kim, Chang-Hwoi;Kim, Jung-So;Jung, Chul-Hwan;Seong, Poong-Hyun
    • Proceedings of the Korean Nuclear Society Conference
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    • 1996.11a
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    • pp.85-90
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    • 1996
  • In this paper, the self-organizing fuzzy logic controller is developed for water level control of steam generator. In comparison with conventional fuzzy logic controllers, this controller performs control task with no control rules at initial and creates control rules as control behavior goes on, and also modifies its control structure when uncertain disturbance is suspected. Selected parameters in the fuzzy logic controller are updated on-line by the gradient descent loaming algorithm based on the performance cost function. This control algorithm is applied to water level control of steam generator model developed by Lee, et al. The computer simulation results confirm good performance of this control algorithm in all power ranges. This control algorithm can be expected to be used for automatic control of feedwater control system in the nuclear power plant with digital instrumentation and control systems.

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Design of a New Capsule Controlling Neutron Flux and Fluence and Temperature of lest Specimen

  • Choo, Kee-Nam;Kang, Young-Hwan;Taiji Hoshiya;Motoji Niimi;Takashi Saito
    • Nuclear Engineering and Technology
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    • v.29 no.2
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    • pp.148-157
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    • 1997
  • A new capsule that has a unique structure in which the test environments including neutron flux and fluence, and irradiation temperature can be controlled precisely during irradiation, was conceptually designed. The capsule structure and instrumentation were successfully designed according to the JMTR's standard procedures of capsule design. Based on the target irradiation, the details of the irradiation such as neutron fluence and irradiation temperature ore calculated and the related capsule safety was evaluated. In addition, the effects of design parameters including the changes in inner-capsule configuration, heater capacity, and Helium gas pressure on the specimen temperature were analyzed with a computer program. Through these thermal and strength evaluations, this capsule was proved to be safe during the irradiation in the JMTR.

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Free Vibration Analysis of Perforated Plates Using Equivalent Elastic Properties

  • Park, Suhn;Jeong, Kyeong-Hoon;Kim, Tae-Wan;Kim, Kang-Soo;Park, Keun-Bae
    • Nuclear Engineering and Technology
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    • v.30 no.5
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    • pp.416-423
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    • 1998
  • Many studies for the perforated plates have been done, especially on the subject of static behavior and stress distribution in the plate. Equivalent elastic properties are one of the successive concepts for this problem. However little effort was taken to get their dynamic characteristics. In this paper finite element modal analysis was performed for the perforated plates having square and triangular hole patterns. An attempt to use existing equivalent elastic properties into the modal analysis of the plate was carried out. To verify feasibility of the finite element models, modal test was also performed on one typical perforated plate. System parameters such as natural frequencies and mode shapes were extracted and compared with the analysis results.

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ABRASIVE BLASTING TECHNOLOGY FOR DECONTAMINATION OF THE INNER SURFACE OF STEAM GENERATOR TUBES

  • Kim, Gye-Nam;Lee, Min-Woo;Park, Hye-Min;Choi, Wang-Kyu;Lee, Kune-Woo
    • Nuclear Engineering and Technology
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    • v.43 no.5
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    • pp.469-476
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    • 2011
  • The inner surfaces of bundled inconel tubes from steam generators in South Korean nuclear power plants are contaminated with cobalt and abrasive blasting equipment has been developed to efficiently remove the cobalt. The principal parameters related to the efficient removal using this equipment are the type of abrasive, the distance from the nozzle, and the blasting time. Preliminary tests were performed using oxidized inconel samples which enabled the simulation of cobalt removal from the radioactive inconel samples. The oxygen in the oxidized samples and the cobalt in the radioactive inconel were removed more effectively using the blasting distance, blasting time, and a silicon carbide abrasive. Using the developed abrasive blasting equipment, the optimum decontamination conditions for radioactive inconel samples were blasting for more than 6 minutes using silicon carbides under 5 atmospheric pressures.

A Design of PWR Hydraulic Test Facility at KAERI

  • Oh, Dong-Seok;Shin, Chang-Whan;In, Wang-Kee;Chun, Tae-Hyun;Jung, Yeun-Ho
    • Proceedings of the Korean Nuclear Society Conference
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    • 2005.05a
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    • pp.13-14
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    • 2005
  • KAERI is performing a project on out-pile test technology development for a full scale PWR fuel assembly. We have introduced the hydraulic test facility, a test assembly, test parameters, test methods, and a data acquisition system. The start up test will be in the middle of March 2005 and the main test will be accomplished by the end of 2006. The established test facility and measuring technique will contribute to the satisfaction of domestic needs for the design verification to improve the reliability of a PWR plant operation.

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Evaluation of Saxton Critical Experiments

  • Joo, Hyung-Kook;Noh, Jae-Man;Jung, Hyung-Guk;Kim, Young-Il;Kim, Young-Jin
    • Proceedings of the Korean Nuclear Society Conference
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    • 1997.10a
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    • pp.191-196
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    • 1997
  • As a part of International Criticality Safety Benchmark Evaluation Project (ICSBEP), SAXTON critical experiments were reevaluated. The effects on $K_{eff}$ of the uncertainties in experiment parameters, fuel rod characterization, soluble boron, critical water level, core structure, $^{241}$ Am and $^{241}$ Pu isotope number densities, random pitch error, duplicated experiment, axial fuel position, model simplification, etc., were evaluated and added in benchmark-model $k_{eff}$. In addition to detailed model, the simplified model for Saxton critical experiments was constructed by omitting the top, middle, and bottom grids and ignoring the fuel above water.r.r.

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Characteristics of NiO films prepared by atomic layer deposition using bis(ethylcyclopentadienyl)-Ni and O2 plasma

  • Ji, Su-Hyeon;Jang, Woo-Sung;Son, Jeong-Wook;Kim, Do-Heyoung
    • Korean Journal of Chemical Engineering
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    • v.35 no.12
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    • pp.2474-2479
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    • 2018
  • Plasma-enhanced atomic layer deposition (PEALD) is well-known for fabricating conformal and uniform films with a well-controlled thickness at the atomic level over any type of supporting substrate. We prepared nickel oxide (NiO) thin films via PEALD using bis(ethylcyclopentadienyl)-nickel ($Ni(EtCp)_2$) and $O_2$ plasma. To optimize the PEALD process, the effects of parameters such as the precursor pulsing time, purging time, $O_2$ plasma exposure time, and power were examined. The optimal PEALD process has a wide deposition-temperature range of $100-325^{\circ}C$ and a growth rate of $0.037{\pm}0.002nm$ per cycle. The NiO films deposited on a silicon substrate with a high aspect ratio exhibited excellent conformality and high linearity with respect to the number of PEALD cycles, without nucleation delay.

UNCERTAINTY EVALUATIONS OF CASMO-3/MASTER SYSTEM FOR PWR CORE NEUTRONICS CALCULATIONS

  • Song, Jae-Seung;Kim, Kang-Seog;Lee, Kibog;Park, Jin-Ha;Zee, Sung-Quun
    • Proceedings of the Korean Nuclear Society Conference
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    • 1996.05a
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    • pp.244-250
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    • 1996
  • Uncertainties in core neutronic calculations of CASMO-3/MASTER, which is a KAERI developed core nuclear design code system, were evaluated via comparisons with measured data. Comparisons were performed with plant measurement data from one Westinghouse type and one ABB-CE type plant and two Korean standard type plants. The CASMO-3/MASTER capability and levels of accuracy are concluded to be sufficient for the neutronics design including safety related parameters related with reactivity, power distributions, temperature and power coefficients, inverse boron worth and control bank worth.

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Loss of a Main Feedwater Pump Test at 100% Power Simulation using Korean Standard Nuclear Plant Analyzer (KSNPA)

  • Jeong, Won-Sang;Kim, Shin-Whan;Sung, Kang-Sik;Seo, Jong-Tae;Lee, Sang-Keun
    • Proceedings of the Korean Nuclear Society Conference
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    • 1996.05a
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    • pp.296-302
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    • 1996
  • The Loss of a Main Feedwater Pump test at 100% Power for YGN 4 was simulated in order to verify and validate the KSNPA. The comparison of the test data with the KSNPA prediction results showed reasonable agreement in the trends of the major plant parameters. All plant control systems including NSSS and T/G control systems are properly actuated and stabilized the plant conditions to a new steady state conditions in the KSNPA. From the comparison results, the KSNPA showed its capability to simulate the LOMFP event for the Korean Standard Nuclear Power Plant.

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