• Nuclear Engineering and Technology
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• 제52권12호
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• pp.2699-2708
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• 2020

Helical-coil steam generator (HCSG) technology is a major design candidate for small modular reactors due to its compactness and capability to produce superheated steam with high generation efficiency. In this paper, we investigate the feasibility of the passively autonomous power maneuvering by coupling the 3-D transient multi-physics of a soluble-boron-free (SBF) core with a time-dependent HCSG model. The predictor corrector quasi-static method was used to reduce the cost of the transient 3-D neutronic solution. In the numerical system simulations, the feedwater flow rate to the secondary of the HCSGs is adjusted to extract the demanded power from the primary loop. This varies the coolant temperature at the inlet of the SBF core, which governs the passively autonomous power maneuvering due to the strongly negative coolant reactivity feedback. Here, we simulate a 100-50-100 load-follow operation with a 5%/minute power ramping speed to investigate the feasibility of the passively autonomous load-follow in a 450 MW_th SBF PWR. In addition, the passively autonomous frequency control operation is investigated. The various system models are coupled, and they are solved by an in-house Fortran-95 code. The results of this work demonstrate constant steam temperature in the secondary side and limited variation of the primary coolant temperature. Meanwhile, the variations of the core axial shape index and the core power peaking are sufficiently small.

• 전력전자학회:학술대회논문집
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• 전력전자학회 2011년도 추계학술대회
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• pp.293-294
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• 2011

본 논문에서는 유성기어를 사용한 직병렬 혼합형 하이브리드 자동차(SPHEV)의 파워트레인 모델링과 하이브리드 자동차의 모드(전기자동차 모드(EV), 엔진 모드, 하이브리드 모드(HEV) 등등)변화에 따른 파워 분배 및 동특성 해석에 대하여 기술한다. 내연기관, 전동기, Energy Storage System(ESS)과 같은 구성요소들의 정격은 에너지 개념과 Electrical Peaking Hybrid(ELPH)를 이용하여 설계하였으며, 동특성 분석을 위하여 전력전자 분야 에서 널리 사용되고 있는 시뮬레이션 툴인 PSIM을 이용하여 모델링 하였다.

• Nuclear Engineering and Technology
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• 제46권3호
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• pp.407-412
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• 2014

In this research, we investigated the burnup characteristics and the conversion of fertile $^{232}Th$ into fissile $^{233}U$ in the core of a Sodium-Cooled Fast Reactor (SFR). The SFR fuel assemblies were designed for burning $^{232}Th$ fuel (fuel pin 1) and $^{233}U$ fuel (fuel pin 2) and include mixed minor actinide compositions. Monte Carlo simulations were performed using Serpent Code1.1.19 to compare with CRAM (Chebyshev Rational Approximation Method) and TTA (Transmutation Trajectory Analysis) method in the burnup calculation mode. The total heating power generated in the system was assumed to be 2000 MWth. During the reactor operation period of 600 days, the effective multiplication factor (keff) was between 0.964 and 0.954 and peaking factor is 1.88867.

• KIEE International Transactions on Power Engineering
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• 제5A권2호
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• pp.199-203
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• 2005

This paper proposes the level of price cap in the TWBP(Two- Way Bidding Pool) market in Korea for which the draft of market design has been prepared by KPX. Max - GMCP(Maximum Generation Market Clearing Price) and APC(Administered Price Cap) would be separately applied as individual price caps for a normal period and a Price Capping period in TWBP. The level of price cap is determined for inducing optimal investment in the Korean Electricity Market considering the 'electricity resource baseline plan' published by the Korean government in 2002 for maintaining government-leading resource planning in Korea. In this regard, Max - GMCP is calculated from the equilibrium condition of investment based on reliability standard and fixed cost of the peaking plant. For verifying the propriety of the proposed price cap, this paper compares the proposed value with the estimated VoLL(Value of Lost Load) based on Korea's GDP(Gross Domestic Product).

• 한국전자파학회논문지
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• 제17권6호
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• pp.538-545
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• 2006

본 논문에서 는 WCDMA(Wideband Code Division Multiple Access) 기지국용 고출력 비 대칭 도허티 전력 증폭기를 구현하였다. 구현된 도허티 증폭기는 P1 dB로부터 9 dB의 영역에 걸쳐 높은 효율을 가지며, 전체 동적 영역에서 선형적인 특성을 갖는다. 고효율 구간의 확장과 선형적인 동적 영역 특성을 얻기 위해서 주 증폭기의 소자보다 두 배 큰 피킹 소자를 사용했으며, 입력에는 비대칭 전력 분배기를 사용하였다. WCDMA 1FA(Frequency Assignment) 신호를 사용하여 측정한 결과 P1 dB로부터 9 dB 백-오프 지점에서 31 %의 전력 부가 효율과 -35 dBc의 ACLR(Adjacent Channel Leakage Power) 특성을 얻었다.

• JSTS:Journal of Semiconductor Technology and Science
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• 제7권1호
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• pp.28-35
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• 2007

This paper presents a high-speed flash analog-to-digital converter (ADC) for ultra wide band (UWB) receivers. In this flash ADC, the interpolating technique is adopted to reduce the number of the amplifiers and a linear and wide-bandwidth interpolating amplifier is presented. For this ADC, the transistor size for the cascaded stages is inversely scaled to improve the trade-off in bandwidth and power consumption. The active inductor peaking technique is also employed in the pre-amplifiers of comparators and the track-and-hold circuit to enhance the bandwidth. Furthermore, a digital-to-analog converter (DAC) is embedded for the sake of measurements. This chip has been fabricated in $0.13{\mu}m$ 1P8M CMOS process and the total power consumption is 113mW with 1V supply voltage. The ADC achieves 4-bit effective number of bits (ENOB) for input signal of 200MHz at 5-GSample/sec.

• 대한전자공학회논문지TC
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• 제41권4호
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• pp.51-58
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• 2004

본 논문에서는 발룬(Balun) 임피던스 트랜스포머(transformer)를 이용한 새로운 구조의 도허티 증폭기를 설계하였다. 도허티 증폭기의 보조 증폭기는 부하변조를 위해 낮은 출력 영역에서 동작이 되지 않도록 설계되며, 일반적으로 보조 증폭기가 동작하지 않는 경우 증폭기의 출력 임피던스는 개방이 된다고 가정한다. 그러나 실제로 구현된 보조 증폭기의 출력 일피던스는 출력단 정합회로의 임피던스 변환 효과에 의해 개방이 아닌 낮은 임피던스 값을 갖게 된다. 본 논문에서는 상기와 같은 보조 증폭기의 특성을 이용하여 새로운 방식의 푸쉬풀 구조 도허티 증폭기를 설계하였다. 제작된 도허티 증폭기는 2개 반송파의 WCDMA 입력 신호에 대하여 출력전력 40㏈m에서 5㎒ 오프셋 주파수 인접채널 누설전력 비율 －37.3㏈c와 23.7%의 효율 특성을 나타내었다.

• Nuclear Engineering and Technology
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• 제53권8호
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• pp.2454-2463
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• 2021

The objective of this research is to the use of americium (AmO₂) as a burnable absorber effectively instead of conventional gadolinium (Gd₂O₃) for VVER-1200 reactor by analyzing its impacts on reactivity, power peaking factor (PPF), safety factor, and quality of the spent fuel. The assembly is burned to 60 GWd/t by using SRAC-2006 code and JENDL-4.0 data library for finding the optimum amount and effective way of using AmO₂ as a burnable absorber. From these studies, it is found that AmO₂ can decrease the excess reactivity like Gd₂O₃ without changing the criticality life span and enrichment of ²³⁵U. A homogeneous mixture of the 0.20% AmO₂+ 4.95% enriched UO₂ fuel rod (model MF-4) decreases the PPF than the reference assembly. The use of AmO₂+UO₂ in the integral burnable absorber (IBA) rod or the outer layer could also decrease the PPF up to 10 GWd/t but increases rapidly after 30 GWd/t, which could be a safety threat. The fuel temperature coefficient and void coefficient of the model MF-4 are the same as the reference assembly. In addition, 22% of initially loaded Am are burning effectively and contributing to the power production.

• Nuclear Engineering and Technology
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• 제44권3호
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• pp.273-282
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• 2012

A new effective methodology for optimizing the enrichment of low-enriched zones as well as gadolinia fuel ($UO_2/Gd_2O_3$) rod designs in PLUS7 fuel assemblies was developed to minimize the maximum peak power in the core and to maximize the cycle lifetime. An automated link code was developed to integrate the genetic algorithm (GA) and the core design code package of ALPHA/PHOENIX-P/ANC and to generate and evaluate the candidates to be optimized efficiently through the integrated code package. This study introduces an optimization technique for the optimization of gadolinia fuel rod designs in order to effectively reduce the peak powers for a few hot assemblies simultaneously during the cycle. Coupled with the gadolinia optimization, the optimum enrichments were determined using the same automated code package. Applying this technique to the reference core of Ulchin Unit 4 Cycle 11, the gadolinia fuel rods in each hot assembly were optimized to different numbers and positions from their original designs, and the maximum peak power was decreased by 2.5%, while the independent optimization technique showed a decrease of 1.6% for the same fuel assembly. The lower enrichments at the fuel rods adjacent to the corner gap (CG), guide tube (GT), and instrumentation tube (IT) were optimized from the current 4.1, 4.1, 4.1 w/o to 4.65, 4.2, 4.2 w/o. The increase in the cycle lifetime achieved through this methodology was 5 effective full-power days (EFPD) on an ideal equilibrium cycle basis while keeping the peak power as low as 2.3% compared with the original design.

• Nuclear Engineering and Technology
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• 제51권2호
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• pp.356-368
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• 2019

This paper presents the verification and validation (V&V) of the STREAM/RAST-K 2.0 code system for a pressurized water reactor (PWR) analysis. A lattice physics code STREAM and a nodal diffusion code RAST-K 2.0 have been developed by a computational reactor physics and experiment laboratory (CORE) of Ulsan National Institute of Science and Technology (UNIST) for an accurate two-step PWR analysis. The calculation modules of each code were already verified against various benchmark problems, whereas this paper focuses on the V&V of linked code system. Three PWR type reactor cores, OPR-1000, three-loop Westinghouse reactor core, and APR-1400, are selected as V&V target plants. This code system, for verification, is compared against the conventional code systems used for the calculations in nuclear design reports (NDRs) and validated against measured plant data. Compared parameters are as follows: critical boron concentration (CBC), axial shape index (ASI), assembly-wise power distribution, burnup distribution and peaking factors. STREAM/RAST-K 2.0 shows the RMS error of critical boron concentration within 20 ppm, and the RMS error of assembly power within 1.34% for all the cycles of all reactors.