• Nuclear Engineering and Technology
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• 제21권4호
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• pp.294-301
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• 1989

상하부 2개의 노외계측기, 노입구관 온도 및 제어봉 위치 신호를 이용하여 상세한 축방향 출력분포를 계산할 수 있는 APDMS프로그램을 개발하였다. 상하부 2개의 노외계측기 신호가 제어봉 위치에 의하여 결정된 제어봉 간섭계수와 노입구관 온도에 따른 온도 간섭계수에 대하여 보정된 후 노심 주변출력을 얻기 위하여 보정된 노외계측기 신호에 shape annealing matrix가 적용되었다. 노심의 상하부 경계에서의 출력을 얻기 위해서는 평균 노심출력과 주변출력과의 선형적 관계를 이용한 노심 상하부의 평균출력에 경계점 출력보정계수가 적용되었다. 축방향 출력분포가 2개의 노외계측기에 의해 계산된 상하부 평균 노심출력, 상하부 경계면에서의 출력 및 미리 계산된 노심의 중심 위치에서의 출력을 이용하여 spline approximation에 의하여 계산되었다. 연소도, 출력준위, 제어봉 위치 및 axial offset의 변화에도 불구하고 고리 3호기 4주기에 대하여 BOXER 코드와 APDMS 프로그램에 의해 계산된 축방향 출력분포의 비교는 5% root mean square 오차내에서 일치함을 보여 주었다.

• 한국군사과학기술학회지
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• 제13권4호
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• pp.542-550
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• 2010

Cooled infrared detector is widely used as the core part in a variety of the thermal imaging systems. For the selection of the highly reliable cooled infrared detector with good performance, it is necessary for us to possess the characterization methods of the well defined performance index of cooled infrared detector. In this paper, various performance index of the cooled infrared detector including reliability as well as the optical and cooling performance of cooled infrared detector are defined and their characterization methods will be investigated and implemented systematically.

• Nuclear Engineering and Technology
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• 제48권6호
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• pp.1291-1302
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• 2016

This paper presents a new and efficient scheme to determine the optimal neutron source position in a model near-equilibrium pressurized water reactor, which is based on the OPR1000 Hanul Unit 3 Cycle 7 configuration. The proposed scheme particularly assigns importance of source positions according to the local adjoint flux distribution. In this research, detailed pin-by-pin reactor adjoint fluxes are determined by using the Monte Carlo KENO-VI code from solutions of the reactor homogeneous critical adjoint transport equations. The adjoint fluxes at each allowable source position are subsequently ranked to yield four candidate positions with the four highest adjoint fluxes. The study next simulates ex-core detector responses using the Monte Carlo MAVRIC code by assuming a neutron source is installed in one of the four candidate positions. The calculation is repeated for all positions. These detector responses are later converted into an inverse count rate ratio curve for each candidate source position. The study confirms that the optimal source position is the one with very high adjoint fluxes and detector responses, which is interestingly the original source position in the OPR1000 core, as it yields an inverse count rate ratio curve closest to the traditional 1/M line. The current work also clearly demonstrates that the proposed adjoint flux-based approach can be used to efficiently determine the optimal geometry for a neutron source and a detector in a modern pressurized water reactor core.

• Nuclear Engineering and Technology
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• 제49권1호
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• pp.141-147
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• 2017

Mechanical shim is an advanced technology for reactor power and axial offset control with control rod assemblies. To address the adverse accuracy impact on the ex-core power range neutron flux measurements-based axial offset control resulting from the variable positions of control rod assemblies, the lead-lag-compensated in-core self-powered vanadium detector signals are utilized. The prompt ${\gamma}$ current of self-powered detector is ignored normally due to its weakness compared with the delayed ${\beta}$ current, although it promptly reflects the flux change of the core. Based on the features of the prompt ${\gamma}$ current, a method for configuration of the lead-lag dynamic compensator is proposed. The simulations indicate that the method can improve dynamic response significantly with negligible adverse effects on the steady response. The robustness of the design implies that the method is of great value for engineering applications.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1996년도 춘계학술발표회논문집(1)
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• pp.459-464
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• 1996

The 3-D power distribution synthesis scheme was implemented in Totally Integrated Core Operation Monitoring System (TICOMS), which is under development as the next generation core monitoring system. The on-line 3-D core power distribution obtained from the measured fixed incore detector readings is used to construct the hot pin power as well as the core average axial power distribution. The core average axial power distribution and the hot pin power of TICOMS were compared with those of the current digital on-line core monitoring system, COLSS, which construct the core average axial power distribution and the pseudo hot pin power. The comparison shows that TICOMS results in the slightly more accurate core average axial power distribution and the less conservative hot pin power. Therefore, these results increased the core operating margins. In addition, the on-line 3-D power distribution is expected to be very useful for the core operation in the future.

• 시스템엔지니어링워크숍
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• 통권4호
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• pp.123-134
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• 2004

This paper deals with the feasibility analysis and alternatives for infrared detector development. The purpose of this paper analyze development requirement and feasibility study in both technology and cost. We get raw input data for system engineering process from development and technical expert, and then analyze cost and technology for development feasibility, and alternative study. Infrared Detector is core component of Thermal Imaging System and developed by ADD from 2006 to 2008 year. Technical level is analyzed by TRL(Technical Readiness Level) and AOA(Analysis of Alternative) is done by development and production cost estimate. We use SEER-H tool for cost estimate, that is parametric cost estimate tool based on Knowledge Base. Also this paper presents risk analysis for project management because it is necessary to risk driver management during the infrared detector development. The result of IR Detector feasibility and alternative study will be used in technical and cost analysis. This study can help those who are related to the cost analysis and development feasibility of other weapons

• 한국정밀공학회:학술대회논문집
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• 한국정밀공학회 2004년도 추계학술대회 논문집
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• pp.60-63
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• 2004

An innovative in-core neutron flux mapping system has been developed and applied successfully for service in a commercial pressurized water reactor. With the benefit of double indexing path selector (Dip $s^{ⓡ}$) mechanism, the reliability of the detector drive system has been improved five times higher than that of conventional systems, and the problems caused by the serious friction generated between the detector cable and guide tubing has been solved completely because the Dip $s^{ⓡ}$ architecture allows the detector guide tubings to have larger curvature and shorter length in nature. The simple and fast maintenance is particularly emphasized in the detector drive system to secure minimum radiation exposure to the maintenance personnel by optimizing the number of components and providing easy access to the components. The programmable logic controller based digital controller with Window $s^{ⓡ}$ based operator s console provides fully automated and user friendly operation and maintenance support means.

• 센서학회지
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• 제25권3호
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• pp.229-234
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• 2016

Self-powered neutron detector (SPND) is being widely used to monitor the reactor core of the nuclear power plants. The SPND contains a neutron-sensitive metallic emitter surrounded by a ceramic insulator. Currently, the vanadium (V) SPND has been being developed to be used in OPR1000 nuclear power plants. Some Monte Carlo simulations were accomplished to calculate the initial sensitivity of vanadium emitter material and alumina insulator with a cylindrical geometry. An MCNP code was used to simulate some factors (neutron self-shielding factor and beta escape probability from the emitter) and space charge effect of an insulator necessary to calculate the sensitivity of vanadium detector. The simulation results were compared with some theoretical and experimental values. The method presented here can be used to analyze the optimum design of the vanadium SPND and contribute to the development of TMI (Top-mount In-core Instrumentation) which might be used in the SMART and SMR.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2001년도 추계학술대회 논문집 전기기기 및 에너지변환시스템부문
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• pp.36-38
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• 2001

A neutron controls a nuclear fission in the core of a reactor. Drive system for in-core neutron detector is an equipment that drives the detector and cable to survey neutron flux in the reactor. The drive system introduced by this paper was designed for mock-up system and fabricated to drive two drivers that having a different function. The system consists of a driver assembly, a power transmission part, and cable storage part. And there is a control panel that contains PLC and inverter. This paper is going to introduce the design and certify the operation status of completed system by control panal. And we conducted the test for torque measurement.

• Nuclear Engineering and Technology
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• 제53권11호
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• pp.3528-3542
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• 2021

A detailed geometrical model of a Krško reactor core was developed using a Monte Carlo neutron transport code MCNP. The main goal of developing an MCNP core model is for it to be used in future research focused on ex-core calculations. A script called McCord was developed to generate MCNP input for an arbitrary fuel cycle configuration from the diffusion based core design package CORD-2, taking advantage of already available material and temperature data obtained in the nuclear core design process. The core model was used to calculate 3D power density profile inside the core. The applicability of the calculated power density distributions was tested by comparison to the CORD-2 calculations, which is regularly used for the nuclear core design calculation verification of the Krško core. For the hot zero power and hot full power states differences between MCNP and CORD-2 in the radial power density profile were <3%. When studying axial power density profiles the differences in axial offset were less than 2.3% for hot full power condition. To further confirm the applicability of the developed model, the measurements with in-core neutron detectors were compared to the calculations, where differences of 5% were observed.