• 한국방사선학회논문지
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• 제9권4호
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• pp.213-217
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• 2015

스텐트 삽입술을 시행한 환자에게 ASL 방법 중 pCASL을 이용한 관류영상에서 나타난 인공물을 보고하고 이에 대한 해결방법을 제시하고자 한다. pCASL데이터는 구조적 이미지와 함께 스텐트를 피해 표지 펄스(labeling pulse)의 위치를 변경하여 획득하였다. 데이터는 ASLtbx를 이용하여 처리하였다. pCASL을 이용하여 관류영상을 획득하였을 때 기존의 표지 펄스(표지 간격(labeling gap) 24 mm)의 위치가 스텐트의 위치와 겹쳐져서 우뇌 조직의 신호강도가 비어 있는 것처럼 나타났다. 스텐트를 피해 표지 펄스(표지 간격 15 mm)를 위치시킬 때 높은 신호강도의 영상을 획득할 수 있었으며, 표지 펄스(표지 간격 170 mm)에서는 labeled 혈액이 영상절편에 도달하기 전에 이완이 되어 낮은 신호강도의 영상을 획득 하였다. pCASL은 조영제를 사용하지 않기 때문에 안정적으로 반복측정이 가능하며 양질의 영상 획득을 위해서는 알맞은 영상획득인자와 방법들이 선택되어야 한다.

• Nuclear Engineering and Technology
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• 제49권6호
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• pp.1326-1338
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• 2017

The continuous energy Monte Carlo neutron transport code, MC21, was coupled to the CTF subchannel thermal-hydraulics code using a combination of Consortium for Advanced Simulation of Light Water Reactors (CASL) tools and in-house Python scripts. An MC21/CTF solution for VERA Core Physics Benchmark Progression Problem 6 demonstrated good agreement with MC21/COBRA-IE and VERA solutions. The MC21/CTF solution for VERA Core Physics Benchmark Progression Problem 7, Watts Bar Unit 1 at beginning of cycle hot full power equilibrium xenon conditions, is the first published coupled Monte Carlo neutronics/subchannel T-H solution for this problem. MC21/CTF predicted a critical boron concentration of 854.5 ppm, yielding a critical eigenvalue of $0.99994{\pm}6.8E-6$ (95% confidence interval). Excellent agreement with a VERA solution of Problem 7 was also demonstrated for integral and local power and temperature parameters.

• Nuclear Engineering and Technology
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• 제49권6호
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• pp.1240-1249
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• 2017

An essential component of the neutron transport solver is the resonance self-shielding calculation used to determine equivalence cross sections. The neutron transport code, MPACT, is currently using the subgroup self-shielding method, in which the method of characteristics (MOC) is used to solve purely absorbing fixed-source problems. Recent efforts incorporating multigroup kernels to the MOC solvers in MPACT have reduced runtime by roughly $2{\times}$. Applying the same concepts for self-shielding and developing a novel lumped parameter approach to MOC, substantial improvements have also been made to the self-shielding computational efficiency without sacrificing any accuracy. These new multigroup and lumped parameter capabilities have been demonstrated on two test cases: (1) a single lattice with quarter symmetry known as VERA (Virtual Environment for Reactor Applications) Progression Problem 2a and (2) a two-dimensional quarter-core slice known as Problem 5a-2D. From these cases, self-shielding computational time was reduced by roughly $3-4{\times}$, with a corresponding 15-20% increase in overall memory burden. An azimuthal angle sensitivity study also shows that only half as many angles are needed, yielding an additional speedup of $2{\times}$. In total, the improvements yield roughly a $7-8{\times}$ speedup. Given these performance benefits, these approaches have been adopted as the default in MPACT.

• Nuclear Engineering and Technology
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• 제52권5호
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• pp.878-888
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• 2020

This paper presents the validation of UNIST in-house Monte Carlo code MCS used for the high-fidelity simulation of commercial pressurized water reactors (PWRs). Its focus is on the accurate, spatially detailed neutronic analyses of startup physics tests for the initial core of the Watts Bar Nuclear 1 reactor, which is a vital step in evaluating core phenomena in an operating nuclear power reactor. The MCS solutions for the Consortium for Advanced Simulation of Light Water Reactors (CASL) Virtual Environment for Reactor Applications (VERA) core physics benchmark progression problems 1 to 5 were verified with KENO-VI and Serpent 2 solutions for geometries ranging from a single-pin cell to a full core. MCS was also validated by comparing with results of reactor zero-power physics tests in a full-core simulation. MCS exhibits an excellent consistency against the measured data with a bias of ±3 pcm at the initial criticality whole-core problem. Furthermore, MCS solutions for rod worth are consistent with measured data, and reasonable agreement is obtained for the isothermal temperature coefficient and soluble boron worth. This favorable comparison with measured parameters exhibited by MCS continues to broaden its validation basis. These results provide confidence in MCS's capability in high-fidelity calculations for practical PWR cores.

• Nuclear Engineering and Technology
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• 제51권4호
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• pp.968-976
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• 2019

This paper presents a number of verification case studies for a recently developed sensitivity/uncertainty code package. The code package, ROMUSE (Reduced Order Modeling based Uncertainty/Sensitivity Estimator) is an effort to provide an analysis tool to be used in conjunction with reactor core simulators, in particular the Virtual Environment for Reactor Applications (VERA) core simulator. ROMUSE has been written in C++ and is currently capable of performing various types of parameter perturbations and associated sensitivity analysis, uncertainty quantification, surrogate model construction and subspace analysis. The current version 2.0 has the capability to interface with the Design Analysis Kit for Optimization and Terascale Applications (DAKOTA) code, which gives ROMUSE access to the various algorithms implemented within DAKOTA, most importantly model calibration. The verification study is performed via two basic problems and two reactor physics models. The first problem is used to verify the ROMUSE single physics gradient-based range finding algorithm capability using an abstract quadratic model. The second problem is the Brusselator problem, which is a coupled problem representative of multi-physics problems. This problem is used to test the capability of constructing surrogates via ROMUSE-DAKOTA. Finally, light water reactor pin cell and sodium-cooled fast reactor fuel assembly problems are simulated via SCALE 6.1 to test ROMUSE capability for uncertainty quantification and sensitivity analysis purposes.

• Journal of Astronomy and Space Sciences
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• 제19권1호
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• pp.47-56
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• 2002

2000년 11월 21일부터 23일가지 3일간 식쌍성 V65l Cas의 극심시각 관측을 수행하였다. 이 관측으로부터 총7개의 새로운 극심시각을 얻었다. 이 관측치를 포함한 V651 Cas의 광전관측 및 CCD 극심시각을 재분석하여, 김천휘와 이재우(2000)가 제안한 제3 천체에 의한 광시간 궤도를 확인하였고, 개선하였다. 최종적으로 구한 광시간 궤도의 주기, 반-진폭, 그리고 이심율은 각각 $6.^{y}3,\;0.^{d}0013$, 그리고 0.78이다. 제3 천체의 궤도경사각이 $30^{\circ}$보다 클 경우, 제3 천체의 질량은 $0.09M_{\odot}\;{\leq}\;M_3\;{\leq}\;0.20M_{\odot}$의 범위에 있다. V65l Cas 계에 상정된 제3 천체가 진실로 존재하고, 주계열성이라면, 그 제3 천체는 주계열 끝에 위치한다.

• Investigative Magnetic Resonance Imaging
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• 제16권2호
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• pp.142-151
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• 2012

목적: 간질중첩증의 동맥 스핀 라벨링 자기공명영상 소견을 알아보고자 한다. 대상과 방법: 본 기관에 내원한 환자들을 대상으로 후향적으로 검색하여 중 간질중첩증으로 임상적으로 진단받았으면서 동맥 스핀 라벨링을 포함한 자기공명영상검사를 받은 환자들을 찾아 이미지를 분석 하였다. 결과: 총 여섯명의 간질중첩증 환자들이 검색되었으며 이 환자들은 모두 EEG에서 이상소견이 나타난 부위에 국소적 CBF증가 소견을 보였다. 특히 두 명의 환자에서는 DWI를 포함한 고식적 자기공명영상 시퀀스에서 모두 특이 소견 보이지 않았으나 동맥 스핀 라벨링 이미지에서만 국소적으로 증가된 CBF를 보였다. 결론: 간질중첩증 환자들의 진단에 있어서 동맥 스핀 라벨링은 기존 영상검사에 더하여 추가적인 역할을 할 수 있을 것으로 기대된다.