• 한국원자력학회:학술대회논문집
• /
• 한국원자력학회 2004년도 추계학술발표회 발표논문집
• /
• pp.657-658
• /
• 2004

The reactor protection system (RPS) of HANARO is a safety class system. The reactor is tripped by dropping four shut off rods (SOR). The SOR system consists of a SOR, hydraulic pump, hydraulic cylinder, solenoid valves and a power supply unit which has the AC coil contactor as a switching component. The hydraulic pump lifts up the SOR. The SOR drops by loss of the hydraulic pressure in the hydraulic circuit at the occurrence of voltage sags or interruptions. From this experiment, we knew that the magnitude of the voltage sag which impacts on this system is 70V, 500msec. The reactor regulation system (RRS) of HANARO has four CARs which are connected to the driver through a magnetic clutch. The CAR drops by loss of electromagnetic force of the magnetic clutch when the deeper voltage sags to lower than 10V, 500msec.

• Nuclear Engineering and Technology
• /
• 제12권2호
• /
• pp.111-120
• /
• 1980

LATREP의 새로운 version인 PHWCELL을 사용하여 월성 CANDU원자로의 핵물리상수를 계산하였다. 이 코드는 주로 중수원자로에 대한 격자상수를 계산하며, 이 코드를 사용하여 중수원 자로의 격자계산의 model 방안을 개발하였다. 본 연구에서 고려된 원자로 운전조건은 Cold Zero Power (CZP)와 Hot Full Power (HFP)로서 독작용이 평형인 상태에서 고려한 것이다. 격자상수는 핵연료의 연소에 대한 것도 고려하였으며, 계산된 결과들은 월성 원자로의 예비안전보고서에 주어진 값과 이전의 연구결과와 비교하였다.

• Nuclear Engineering and Technology
• /
• 제33권2호
• /
• pp.132-144
• /
• 2001

Fracture mechanics is one of the major areas of the pressurized thermal shock (PTS) evaluation. To evaluate the reactor pressure vessel integrity associated with PTS, PFM methodology demands precise calculation of temperature, stress, and stress intensity factor for the variety of PTS transients. However, the existence of stainless steel cladding, with different thermal, physical, and mechanical property, at the inner surface of reactor pressure vessel complicates the fracture mechanics analysis. In this paper, treatment schemes to evaluate stress and resulting stress intensity factor for RPV with stainless steel clad are introduced. For a reference transient, the effects of clad thermal conductivity and thermal expansion coefficients on deterministic fracture mechanics analysis are examined.

• 한국정보과학회:학술대회논문집
• /
• 한국정보과학회 2005년도 한국컴퓨터종합학술대회 논문집 Vol.32 No.1 (B)
• /
• pp.373-375
• /
• 2005

본 논문에서는 최근에 각광을 받고 있는 HLA의 연구 현황을 파악하고 HLA의 기본 개념, 구성 요소, HLA를 이용한 시뮬레이션의 개발 방법 등에 대하여 조사하였다. 그리고 SMART-P 안전해석 전산코드인 TASS/SMR을 HLA에 적용하기 위한 방법에 대하여 기술하였으며 랩퍼 (Wrapper)를 사용하여 TASS/SMR을 HLA에 적용하여 보았다. 이러한 연구 결과로 TASS/SMR을 HLA에 적용, 구현하여 실행됨을 확인하였으며 그 결과로 레거시 코드를 HLA에 적용할 수 있는 방향을 제시하였다.

• Nuclear Engineering and Technology
• /
• 제36권2호
• /
• pp.175-183
• /
• 2004

For the analysis of a dry process fuel cycle, new modules were implemented into the fuel cycle analysis code DYMOND, which was developed by the Argonne National Laboratory. The modifications were made to the energy demand prediction model, a Canada deuterium uranium (CANDU) reactor, direct use of spent pressurized water reactor (PWR) fuel in CANDU reactors (DUPIC) fuel cycle model, the fuel cycle calculation module, and the input/output modules. The performance of the modified DYMOND code was assessed for the postulated once-through fuel cycle models including both the PWR and CANDU reactor. This paper presents modifications of the DYMOND code and the results of sample calculations for the PWR once-though and DUPIC fuel cycles.

• Nuclear Engineering and Technology
• /
• 제9권1호
• /
• pp.15-31
• /
• 1977

중수형 원자력발전소의 가동중에 연료를 재장전하는 특성을 고려하여 새로운 핵연료 batch와 주기의 개념을 서정하고, 연속적인 에너지 계산방법으로 개발하여 핵주기비 계산관계식을 유도하였으며, 이러한 관계식들로서 중수형 원자로에 사용될 수 있는 전자계산기 코드 HWRCOST를 개발하였다. 이 코드로서 현재 우리나라에 건설중인 CANDU-PHWR의 전수명에 걸친 핵연료 주기비를 계산하였고 아울러 우라늄 원광비, 성형 가공비, 사용핵연료 보관처리비 및 발전소 가동율의 변화에 대한 핵연료 주기비의 감응도를 분석하였다.

• Nuclear Engineering and Technology
• /
• 제19권4호
• /
• pp.310-316
• /
• 1987

중성자 확산 방정식의λ -mode를 구하는 반복 계산법을 정립하였고, 이 방법을 이용한 2군, 3차원 전산 코드 MOGEN을 개발하였다. 2차원 직각형 균질 원자로에 대해 계산을 수행하여, 생산된 고유치와 고유함수가 해석해에 잘 일치함을 보여 코드의 정확도를 검증하였다. 실제 CANDU형 포준 원자로의 2차원 mode를 생산하였고, 이는 기존의 mode특성을 정확히 나타내었다. 마지막으로, λ-mode의 응용분야에 대하여 간략히 설명하였다.

• Nuclear Engineering and Technology
• /
• 제56권3호
• /
• pp.1013-1021
• /
• 2024

A series of experiments were performed to produce a fuel source for a molten salt reactor (MSR) through pyroprocessing technology. A simulated LiCl-KCl-UCl₃-NdCl₃ salt system was prepared, and the U element was fully recovered using a liquid cadmium cathode (LCC) by applying a constant current. As a result, the salt was purified with an UCl₃ concentration lower than 100 ppm. Subsequently, the U/RE ingot was prepared by melting U and RE metals in Y₂O₃ crucible at 1473 K as a surrogate for RE-rich ingot product from pyroprocessing. The produced ingot was sliced and used as a working electrode in LiCl-KCl-LaCl₃ salt. Only RE elements were then anodically dissolved by applying potential at - 1.7 V versus Ag/AgCl reference electrode. The RE-removed ingot product was used to produce UCl₃ via the reaction with NH4Cl in a sealed reactor.

• Nuclear Engineering and Technology
• /
• 제49권4호
• /
• pp.752-759
• /
• 2017

The fatigue crack growth behavior of Type 347 (S347) and Type 347N (S347N) stainless steel was evaluated under the operating conditions of a pressurized water reactor (PWR). These two materials showed different fatigue crack growth rates (FCGRs) according to the changes in dissolved oxygen content and frequency. Under the simulated PWR conditions for normal operation, the FCGR of S347N was lower than that of S347 and insensitive to the changes in PWR water conditions. The higher yield strength and better corrosion resistance of the nitrogen-alloyed Type 347 stainless steel might be a main cause of slower FCGR and more stable properties against changes in environmental conditions.

• Nuclear Engineering and Technology
• /
• 제35권5호
• /
• pp.454-470
• /
• 2003

In this paper, a preliminary study for development of a fault diagnosis is presented for monitoring and diagnosing faults in the agitator driving system of a high temperature reduction reactor. In order to identify a fault occurrence and classify the fault cause, vibration signals measured by accelerometers on the outer shroud of the agitator driving system are firstly decomposed by wavelet transform (WT) and the features corresponding to each fault type are extracted. For the diagnosis, the fuzzy ARTMAP is employed and thereby, based on the features extracted from the WT, the robust fault classifier can be implemented with a very short training time - a single training epoch and a single learning iteration is sufficient for training the fault classifier. The test results demonstrate satisfactory classification for the faults pre-categorized from considerations of possible occurrence during experiments on a small-scale reduction reactor.