• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1997년도 춘계학술발표회논문집(2)
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• pp.515-519
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• 1997

The purpose of this study is to reduce the fast neutron fluence at the reactor pressure vessel(RPV) and to provide a basis for plant-life extension. In this study, different neutron absorbers were employed in the core outer assemblies of Kori Unit 1 Cycle 14. The modified assemblies were used to calculate fast neutron fluence at the RPV and to evaluate reduction of outer assembly power and total power in core. By comparison with the case of no suppression fixture, the fast neutron fluence of a case with two rows stainless steel around the assembly with natural uranium pins is decreased by 85.8%. It is noted that the modification of outer assembly is more efficient than the previous low leakage loading pattern (LLLP) applied to Kori Unit 1. Also, compared fast neutron fluence in Cycle 1 with Cycle 14, fast neutron fluence at the RPV between Cycle 1 and Cycle 14 is not significantly different. It is found that LLLP applied to the Kori Unit 1 has not contributed to fast neutron fluence reduction at the RPV.

• Journal of Radiation Protection and Research
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• 제36권4호
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• pp.200-208
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• 2011

Fluence monitor(F/M)는 조사 시편을 원자로의 노심에 넣은 후 방사화 된 조사 시편의 방사능을 측정한 후 역산하여 중성자의 선량을 계산하는 기법으로 원자로내의 중성자 분포를 조사하기 위하여 반드시 필요한 기술이다. 이 기술은 중성자에 대한 에너지 스펙트럼 측정이 간접적으로 가능하며, 현존하는 중성자 분포 측정 기법 중에서 우수한 정밀도를 지니고 있다. 하나로(HANARO)에서 수행하는 재료조사 시험에서의 중성자량 측정을 위하여 본 연구에서는 지름 0.1 mm, 길이 3 mm 미만의 질량 150~200 ${\mu}g$ 범위, 순도 99.9% 이상의 Fe, Ni, Ti 와이어를 F/M 시편으로 사용하였다. 이 시편은 알루미늄 캡슐에 봉입하여 30 MW 의 하나로 OR5공에 약 25일간 조사하였다. 조사를 마친 시편은 high purity germanium (HPGe) detector를 이용하여 감마선을 측정하였고, SAND-II code로 reaction rate와 중성자 cross-section등을 고려하여 fluence monitor 위치에서의 중성자 플루언스를 계산하였다. F/M이 장착 되었던 하나로 OR5공의 중성자 플루언스 값은 MCNP 코드를 이용하여 계산된 결과를 사용하였으며, SAND-II code로 장착된 F/M 위치에서의 중성자 플루언스를 계산하여 적용된 시편의 reaction에 따른 결과값의 차이를 비교 분석하였다.

• Nuclear Engineering and Technology
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• 제31권4호
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• pp.408-422
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• 1999

To reduce the fast neutron fluence which deteriorates the RPV integrity, additional shields were assumed to be installed at the outer core structures of the Kori Unit 1 reactor, and its reduction effects were examined. Full scope Monte Carlo simulation with MCNP4A code was made to estimate the fast neutron fluence at the RPV. An optimized design option was found from various choices in geometry and material for shield structure. It was expected that magnitude of fast neutron fluence would be reduced by 39% at the circumferential weld of the RPV, resulting in extension of plant lifetime by 4.6 EFPYs based on the criterion of PTS requirement It was investigated that the nuclear characteristics and thermal hydraulic factors at the internal core were only negligibly influenced by the installation of additional shield structure.

• Journal of Radiation Protection and Research
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• 제36권1호
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• pp.28-34
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• 2011

세기조절방사선치료(Intensity Modulated Radiotherapy, IMRT)의 정도관리를 위해서 독립적인 방법으로 선량검증을 하는 것은 중요하다. 독립적 선량검증을 위해 팬톰과 이온전리함을 이용한 측정 방법이 보편적으로 이루어지지만 많은 시간과 노력이 요구된다. 본 연구에서는 세기조절방사선치료 시 시간에 따른 다엽콜리메이터의 움직임을 기록한 dynalog 파일을 이용하여 치료계획에서 도출된 총 실제 플루언스와 실제 치료 시의 모니터유닛(monitor unit, MU) 공간분포를 비교함으로써 간편한 세기조절방사선치료 정도관리 기술을 개발하였다. DICOM RT plan 파일로부터 총 실제 플루언스를 추출하고 MATLAB 코드를 이용하여 실제 치료 시 MU 공간분포를 dynalog 파일로부터 계산하였다. 개발된 방법의 효용성을 검증하기 위해 단계별조사기법과 동적조사기법으로 치료 받은 각 5명의 환자 데이터를 후향적으로 분석하였다. 분석 방법은 상용프로그램(Verisoft 3.1, PTW, German)에서 제공하는 감마인덱스를 사용하였다. 분석 결과 실제 치료 시의 MU 공간분포와 치료계획 상의 MU 공간분포 일치도가 평균 $97.8{\pm}1.33$%로 높은 일치도를 나타냈다. MU 공간분포 재구성의 정확도는 동적조사기법보다 단계별조사기법이 평균 1.4% 높았다. 본 연구에서 개발된 기술을 통해 세기조절방사선치료의 선량검증을 효과적으로 수행할 수 있다. 또한 분할치료 시 선량보정에 적용함으로써 맞춤형치료(adaptive radiotherapy)를 위한 기초자료로 사용될 수 있을 것이다.

• 천문학회보
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• 제41권1호
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• pp.82-82
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• 2016

To find the relationship between solar flares and halo CMEs using stereoscopic observations, we investigate 182 flare-associated halo CMEs among 306 front-side halo CMEs from 2009 to 2013. We have determined the 3D parameters (radial speed and angular width) of these CMEs by applying StereoCAT to multi-spacecraft data (SOHO and STEREO). For this work, we use flare parameters (peak flux and fluence) taken from GOES X-ray flare list and 2D CME parameters (projected speed, apparent angular width, and kinetic energy) taken from CDAW SOHO LASCO CME catalog. Major results from this study are as follows. First, the relationship between flare peak flux (or fluence) and CME speed is almost same for both 2D and 3D cases. Second, there is a possible correlation between flare fluence and CME width, which is more evident in 3D case than 2D one. Third, the flare fluence is well correlated with CME kinetic energy (CC=0.63). Fourth, there is an upper limit of CME kinetic energy for a given flare fluence (or peak flux). For example, a possible CME kinetic energy ranges from 1030.6 to 1033 erg for a given X1.0 class flare. Our results will be discussed in view of the physical mechanism of solar eruptions.

• 한국정밀공학회지
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• 제30권10호
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• pp.1009-1015
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• 2013

Ultra-short laser pulses are effective, when high requirements concerning accuracy, surface roughness and heat affected zone are demanded for surface structuring. In particular, picosecond laser systems that are suited to be operated in industrial environments are of great interest for many practical applications. This paper focused on inducing optimum process parameters for higher volume ablation rate by analyzing a relationship between crater diameter and optical spot size. In detail, the dependency of the volume ablation rate, penetration depth and threshold fluence on the pulse duration 8 ps and wavelength of 515 nm was discussed. The experimental results showed that wavelength of 515 nm resulted in less threshold fluence ($0.075J/cm^2$) on copper than IR wavelength ($0.3J/cm^2$). As a result, it was possible that optimum fluence for higher volume ablation rate was achieved with $0.28J/cm^2$.

• Journal of Radiation Protection and Research
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• 제26권3호
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• pp.237-241
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• 2001

The uncertainties associated with fluence calculation at the pressure vessel have been evaluated for the Korean Next Generation Reactor, APR1400. To obtain uncertainties, sensitivity analyses were performed for each of the parameters important to calculated fast neutron fluence. Among the important parameters to the overall uncertainties, reactor modeling and core neutron source were examined. Mechanical tolerances, composition and density variations in the reactor materials as well as application of $r-{\theta}$ geometry in rectilinear region contribute to uncertainty in the reactor modeling. Depletion and buildup of fissile nuclides, instrument error related to core power level, uncertainty of fuel pin burnup, and variation of long-term axial peaking factors are main contributors to the core neutron source uncertainty. The sensitivity analyses have shown that the uncertainty in the fluence calculation at the reactor pressure vessel is +12%.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1998년도 춘계학술발표회논문집(2)
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• pp.771-776
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• 1998

TORT is employed for fast neutron fluence calculation at the reactor pressure vessel. KORI Unit 1 reactor at cycle 1 is modeled for this calculation. Three-dimensional cycle averaged assembly power distributions for KORI Vnit 1 at cycle 1 are calculated by using the core physics code, NESTLE 5.0. The root mean square error is within 4.3% compared with NDR (Nuclear Design Report) far all burnup steps. The C/E (Calculated/Experimental) values for the in-vessel dosimeters distribute between 0.98 and 1.36. The most updated cross-section library. BUGLE-96 based on ENDF/B-VI is used for the neutron fluence calculation. The makimum fast neutron nun calculated on reactor pressure vessel for KORI Unit 1 operated for 411.41 effgctive full power days is 1.784x10$^{18}$ n/$\textrm{cm}^2$. The position of the maximum neutron fluence in RPV wall 1/4 T is nearby 60cm below the midplane at zero degree.

• Nuclear Engineering and Technology
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• 제38권7호
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• pp.665-674
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• 2006

Three-dimensional neutron flux and fluence of Kori Unit 3 were evaluated using the synthesis technique described in Regulatory Guide 1.190 for all reactor geometry. For this purpose DORT neutron transport calculations from Cycle 1 to Cycle 15 were performed using BUGLE-96 cross-section library. The calculated flux and fluence were validated by comparing the calculated reaction rates to the measurement data from the dosimetry sensor set of the $5^{th}$ surveillance capsule withdrawn at the end of cycle 15 of Kori Unit 3. And then the best estimation of the neutron exposures for the reactor vessel beltline region was performed using the least square evaluation. These results can be used in the assessment of the state of embrittlement of Kori Unit 3 pressure vessel.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1996년도 춘계학술발표회논문집(1)
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• pp.64-69
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• 1996

원자로 vessel 수명에 영향을 미치는 fluence를 감소시키는 방안을 고리 1호기에 대하여 검토하였다. 적용 방법은 하드웨어 변경과 향상된 설계 방법론 적용등으로 확보한 열적여유도를 정량화하고, 이를 설계상의 F$_{{\Delta}H}$ 제한치 상향조정에 활용하여 상대적으로 저누출 장전모형을 선정하므로써 vessel fluence를 줄이도록 하였다. 분석 결과, 적절한 열적여유도를 보유하고도 F$_{{\Delta}H}$ 제한치를 7% 정도 높일 수 있는 것으로 밝혀졌으며, 이렇게 상향 조정된 제한치를 사용할 경우 핵연료 이용율 향상과 함께 vessel fluence의 감소 효과를 얻어 vessel의 수명 연장에 도움을 줄 수 있는 것으로 밝혀졌다.