• Nuclear Engineering and Technology
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• 제55권4호
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• pp.1280-1286
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• 2023

MgF₂ as a moderator material has been extensively used in the beam shaping assembly (BSA) that plays an important role in the boron neutron capture therapy (BNCT). Regarded as important for applications, the thermal neutron scattering data of MgF₂ were calculated, based on the phonon expansion model. The structural properties of MgF₂ were researched by the VASP code based on the ab-initio methods. The PHONOPY code was employed to calculate the phonon density of states. Furthermore, the NJOY code was used to calculate the thermal neutron scattering data of MgF₂. The calculated inelastic cross sections plus absorption cross sections are in agreement with the available experimental data. The neutron transport in the BSA has been simulated by using a hybrid Monte-Carlo-Deterministic code NECP-MCX. The results indicated that compared with the calculation of the free gas model, the thermal neutron flux and epithermal neutron flux at the BSA exit port calculated by using the thermal neutron scattering data of MgF₂ were reduced by 27.7% and 8.2%, respectively.

• Transactions on Electrical and Electronic Materials
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• 제9권6호
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• pp.265-272
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• 2008

In this paper, AC losses of long wire Bi-2223 tapes with different twist pitch of superconducting core were fabricated, measured and analyzed. These samples produced by a powder-in-tube method are multi-filamentary tape with Ag matrix. Also, it's produced by non-twist. The critical current measurement was carried out under the environment in Liquid nitrogen and in zero field by 4-prob method. And the Magnetic measurement was carried out under the environment of applied time-varying transport current by transport method. From experiment, the susceptibility measurements were conducted while cooling in a magnetic field. Flux loss measurements were conducted as a function of ramping rate, frequency and field direction. The AC flux loss increases as the twist-pitch of the tapes decreased, in agreement with the Norris Equation. Neutron-diffraction measurements have been carried out investigate the crystal structure, magnetic structures, and magnetic phase transitions in Bi-2223([Bi, Pb]:Sr:Ca:Cu:O).

• Nuclear Engineering and Technology
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• 제22권2호
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• pp.151-158
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• 1990

새로운 중성자 수송방정식의 해법인 Discrete Elements Method(DEM)를 1차원 모델에 대 한 단일 에너지 중성자 수송방정식에 적용했다. 본 연구에서는 고정선원문제와 임계계산을 행하여, 각분할법과 DEM의 계산결과의 정확도를 비교했으며 세가지의 위치차등법(DD, SC그리고 LC Scheme)중 어떤 것이 DEM에서 가장 좋은지를 오차분석을 통해 정량적으로 알아보았다. 수행한 모든 계산결과에서 같은 위치차등법을 이용할 때 DEM결과의 정확도가 각분할법으로 얻은 결과보다 훨씬 좋았으며 위치차등법중에서는 각분할 법에서와 같이 DEM에서도 LC scheme이 가장 좋은 결과를 주었다.

• Nuclear Engineering and Technology
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• 제2권4호
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• pp.249-254
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• 1970

고 에너지 영역에서 비탄성핵을 가진 충격중성자 전도문제에서 시간과 에너지의 과도적인 특성은 연속 에너지 전도연산자로서 면밀히 해결했다. 점근적으로 가장 우세한 하나의 고정된 시간고유치를 발견했다. 완전한 해는 다음 세 부분으로 되어 있다. 1. 점근적으로 가장 우세한 시간과 에너지의 분리 가능형. 2. 과도적으로 감속하는 순 에너지에 의해서 결정된 분리 불가능형. 3. 점근적으로 무시할 수 있는 시간과 에너지의 혼합에 의하여 결정된 분리 불가능형.

• Nuclear Engineering and Technology
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• 제2권4호
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• pp.263-268
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• 1970

시간과 에너지에 종속된 중성자 전도 방정식에 나타나는 연속 에너지 전도 연산자의 스펙트럼(Spectrum)을 분석했다. 스펙트럼에 관한 4가지 정리를 증명하고 일반화된 Mellin 에너지변화의 Convolution 정리를 얻었다. 또한 최종해에 필요한 완전성정리를 증명하고 점근적으로 가장 우세한 시간붕괴상수 1 - c를 발견하였다.

• Nuclear Engineering and Technology
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• 제3권4호
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• pp.203-208
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• 1971

Noether의 이론을 1차원의 중성자 수송방정식에 적용하였다. 1차원의 Boltzmann방정식의 functional을 불변케 하는 변환을 구했으며 이결과 중성자속과 그의 Adjoint 중성자속의 곱이 보존된다는 법칙을 유도하였다. 이 보존법칙으로부터 1차원의 Boltzmann방정식의 가능한 해의 형태를 얻었고 이것을 이미 알려진 해와 비교하였다.

• Nuclear Engineering and Technology
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• 제52권2호
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• pp.448-455
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• 2020

The H.B. Robinson Unit 2 (HBR-2) pressure vessel dosimetry benchmark is an in- and ex-Reactor Pressure Vessel (RPV) neutron dosimetry benchmark based on experimental data from the HBR-2 reactor, a 2300-MW PWR designed by Westinghouse and put in operation in March 1971, openly available through the SINBAD Database at OECD/NEA data Bank. The goals of the present work were to carry out three-dimensional (3D) fixed source transport calculations in both Cartesian (X,Y,Z) and cylindrical (R,θ,Z) geometries by using the TORT-3.2 discrete ordinates code on very detailed 3D HBR-2 geometrical models and to test the latest broad-group coupled (47 neutron groups + 20 photon groups) working cross section libraries in FIDO-ANISN format with same structure as BUGLE-96, such as BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-B7. The results obtained with all the cited libraries were satisfactory and are here reported and compared.

• Journal of Information Processing Systems
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• 제7권1호
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• pp.63-74
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• 2011

As a powerful and flexible processor, the Graphic Processing Unit (GPU) can offer a great faculty in solving many high-performance computing applications. Sweep3D, which simulates a single group time-independent discrete ordinates (Sn) neutron transport deterministically on 3D Cartesian geometry space, represents the key part of a real ASCI application. The wavefront process for parallel computation in Sweep3D limits the concurrent threads on the GPU. In this paper, we present multi-dimensional optimization methods for Sweep3D, which can be efficiently implemented on the finegrained parallel architecture of the GPU. Our results show that the overall performance of Sweep3D on the CPU-GPU hybrid platform can be improved up to 4.38 times as compared to the CPU-based implementation.

• 에너지공학
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• 제15권4호
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• pp.250-255
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• 2006

원자력 분야에서 중성자 수송계산을 위해 개발되어 널리 사용되는 방향차분법을 시간 종속 복사 열전달식의 해를 구하는데 적용하였다. 광자의 방향별 밀도를 자체수반형 2계 편미분방정식으로 나타내어 해의 안정성을 높였고 매질의 온도방정식의 비선형성은 다단계 선형화법을 사용하여 근사하였다. 본 연구에서 개발된 해법을 전형적인 Marshak wave 문제에 적용하였고 계산 결과를 기존의 Monte Carlo의 계산결과와 비교하여 그 우월성을 보였다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1996년도 춘계학술발표회논문집(1)
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• pp.58-63
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• 1996

This paper is devoted to evaluating the accuracy of general 2D geometric transport code, HELIOS, and determining the order of merit in modeling for some important HELIOS input parameters. Benchmark test for 12 critical lattices show that HELIOS predicts criticality accurately within experimental uncertainties, showing only 250 pcm overestimation with a standard deviation of 450 pcm. The sensitivity test suggest that current coupling order, neutron group library, geometrical modeling, and resonance options must be considered carefully to obtain accurate results. Especially, current coupling order and sub-rings in fuel regions turn out to be most critical in HELIOS modeling. For MOX loaded cores, it is additionally necessary to pay attention to the resonance option and the validity of small group neutron library.