The effects of fast neutron irradiation on the electrical and optical properties of Li (3 at%) doped ZnSnO (ZTO) thin films fabricated using a sol-gel process are investigated. From the results of Li-ZTO TFT characteristics according to change of neutron irradiation time, the saturation mobility is found to increase and threshold voltage values shift to a negative direction from 1,000 s neutron irradiation time. X-ray photoelectron spectroscopy analysis of the O 1s core level shows that the relative area of oxygen vacancies is almost unchanged with different irradiation times. From the results of band alignment, it is confirmed that, due to the increase of electron carrier concentration, the Fermi level (EF) of the sample irradiated for 1,000 s is located at the position closest to the conduction band minimum. The increase in electron concentration is considered by looking at the shallow band edge state under the conduction band edge formed by fast neutron irradiation of more than 1,000 s.

Fatigue crack growth retardation of 304 L stainless steel is studied using a neutron diffraction method. Three orthogonal strain components(crack growth, crack opening, and through-thickness direction) are measured in the vicinity of the crack tip along the crack propagation direction. The residual strain profiles (1) at the mid-thickness and (2) at the 1.5 mm away from the mid-thickness of the compact tension(CT) specimen are compared. Residual lattice strains at the 1.5 mm location are slightly higher than at the mid-thickness. The CT specimen is deformed in situ under applied loads, thereby providing evolution of the internal stress fields around the crack tip. A tensile overload results in an increased magnitude of the compressive residual stress field. In the crack growth retardation, it is found that the stresses are dispersed in the crack-wake region, where the highest compressive residual stresses are measured. Our neutron diffraction mapping results reveal that the dominant mechanism is by interrupting the transfer of stress concentration at the crack tip.

The HANARO reactor constructed from Jan. 1985 to April 1995, and a major utilization system, the Cold Neutron Research Facility was completed Nov. 2010. The cold neutron research facility consists of a Cold Neutron Source, a process system, a neutron guide and a Spectrometer. A moderator is utilized to transform thermal neutrons into cold neutrons. A moderator cell accommodates the moderator. The inner assembly contains an aluminum moderator cell connected to a stainless steel heat exchanger by a bi-metallic transition joint. An In-Pool Assembly is welded to this inner assembly and a double flexible pipe, and a vacuum chamber is inserted. After HANARO reactor shutdown, the in-pool assembly was installed at a cold neutron hole in the reactor pool. We confirmed a precise installation by using an underwater TV camera for a nuclear reactor inspection. In-pool assembly connected to double flexible pipe each system in the Cold Neutron Research Facility. After cold neutron research facility operated, the reliability of vacuum system, helium refrigerator system, gas blanket system and hydrogen system for maintenance was confirmed.

Ni-W(1-5 at.%) alloy rods were made by powder metallurgy process including powder mixing, compacting and subsequent sintering. Ni and W powder of appropriate compositions were mixed by a ball milling and isostatically pressed in a rubber mold into a rod. The compacted rods were sintered at at a reduced atmosphere for densification. The lattice parameters of Ni-W alloys were estimated by a high resolution neutron powder diffractometer. All sintered rods were found to have a face centered cubic structure without any impurity phase, but the diffraction peak locations were linearly shifted with increasing W content. The lattice parameter of a pure Ni rod was which is consistent with the value reported in JCPDS data. The lattice parameter of N-W alloy rods increased by for 1 atomic % of W, which indicates the formation of a Ni-W solid solution due to the substitution of nickel atoms by tungsten atoms of larger size.

It is essential to develop the shield for the extraction of high quality neutron beam and safe work at the sample position. The aim of this study is design, fabrication and filling of the shield in domestic. In consideration of ST-3 beam port of HANARO, we designed the reflectometer shield composed of 14 blocks and fabricated it shield casemate. Through the assembly and quality test of the shield casemate, we established the method of fabrication for neutron beam path and channel. In order to increase shield capacity, we filled shield casemate with heavy concrete, lead ingot and polyethylene that mixed B4C powder and epoxy. The average density of the filled heavy concrete was 4.7g/cm3, which can protect neutron and gamma ray effectively. Also, we developed ancillary equipment such as beam gate unit(BGU, vertical type) for the effective opening and closing of neutron beam. Shielding block was proved by suitable thickness as result that measure surface dosage using of detector and TLD. The acquired technique of design, fabrication and filling of ancillary equipment development can be applicable to the development of shield for the other neutron spectrometer in future.

The nano-scale crystallite sizes of uranium oxide powders in simulated spent fuel were measured by the neutron diffraction line broadening method in order to analyze the sintering behavior of the dry process fuel. The mixed and fission product powders were dry-milled in an attritor for 30, 60, and 120 min. The diffraction patterns of the powders were obtained by using the high resolution powder diffractometer in the HANARO research reactor. Diffraction line broadening due to crystallite size was measured using various techniques such as the Stokes' deconvolution, profile fitting methods using Cauchy function, Gaussian function, and Voigt function, and the Warren-Averbach method. The non-uniform strain, stacking fault and twin probability were measured using the information from the diffraction pattern. The realistic crystallite size could be obtained after separation of the contribution from the non-uniform strain, stacking fault and twin.

σ-VFe 금속간화합물에 대한 기계적 합금화(MA) 효과를 중성자 및 X선 회절법으로 조사하였다. MA 분말의 구조분석은 X선 회절(Cu-Kα) 린 중성자회절(HRPD, λ=1.835Å)을 이용하여 행하였다. σ-VFe화합물의 MA시 큰 구조변화가 관찰되었으며, MA 60시간의 경우 Fe-Fe 훤자분포는 unit cell에 30개의 원자를 포함하고 있는 σ상의 tetragonal구조에서 120˚C이상에서 안정하게 존재하는 α-(V,Fe) 고용체의 bcc 구조로 상변화함을 알 수 있었다. 또한 α-VFe 화합물에 대한 중성자 및 X선 회절패턴의 비교분석을 행하였으며 그 결과 σ상이 가지는 화학적 규칙성에 기인하는 (101)과 (111) 회절 피크가 중성자 회절에서 뚜렷하게 관찰됨을 알 수 있었다.

Mn-Mo-Ni 저합금강의 중성자 조사에 따른 기계적(미세경도, 인장, 샤피충격시험) 및 자기적(포화자화, 보자력, 잔류자화, Barkhausen Noise(BN)진폭, BN에너지) 성질 변화를 측정하여 이들의 상관관계를 고찰하였다. 기계적 성질시험 결과, 중성자 조사로 인하여 항복강도, 인장강도, 미세경도 및 천이온도(T41J)는 증가하였고 최대흡수에너지(USE)는 감소하였으며, 인장 시험의 경우 용접금속에서는 모재와 비교했을 때 큰 변화가 없었다. 자기적 성질을 측정한 결과, 잔류자화, BN진폭, BN에너지는 감소하였고 보자력은 급격히 증가하는 것으로 나타났다. 기계적.자기적 성질변화의 상관관계에서 자기적성질인 보자력 증가에 따라 천이온도, 항복강도, 경도는 증가하고 USE는 감소하였고, BN진폭의 경우는 보자력과 반대의 경향을 보였다. 본 실험에서 중성자조사로 인한 기계적.자기적 성질변화가 일관성 있는 상관관계가 있음을 확인하였고, 이들의 변화를 통해 조사손상을 평가하는 데 이용 가능하다.

방사선물질의 수송 및 저장용기 등에 사용되는 에폭시수지계 중섣자 차폐재, KNS-201, KNS-301 및 KNS-601을 제조하였다. 기본물질은 개질 및 수소 첨가된 비스페놀 A형 그리고 노블락형 에폭시수지이며, 첨가제로는 수산화알루미늄 및 탄화붕소이다. 이들 중성자 차폐재들의 열적 및 역학적 성질 및 재방사선성 등을 평가하기 위해 여러 특성시험을 행하였다. 조사된 제반 특성들은 열분해온도;257~280˚C, 열전도도;0.95~1.14W/m.K, 열팽창계수 ;0.77~1.26x10-6˚C-1, 연소특성;800˚C이하, 평균연소시간;5초 이하, 평균연소길이 ;5mm 이하, 인장강도;2.5~3.2Kg/mm2,압축강도:13.2~15.2kg/mm2 굴곡강도:5.2~604Kg/mm2 등을 나타냈다. 전반적으로 개발된 중성자 차폐재들의 관련 특성들이 외국에서 사용되는 중성자 차폐재, NS-4-RF보다 우수한 것으로 나타났다. 또한 KNS-601의 내방사선성이 KNS-201과 KNS-301보다 우수한 것으로 나타났다. 또한 KNS-601의 내방사선이 KNS-201과 KNS-301보다 우수한 것으로 나타났다.

양성자 치료기의 Passive Scattering System 노즐을 모의모사 하여 노즐 내 각 구성품에서 발생되는 중성자를 에너지별로 평가하였다. MCNPX code를 이용하여 치료환경에 사용되는 양성자 에너지 220 MeV, 도달 거리 20 cm, 6 cm 길이의 SOBP를 구현하고, 치료기 가동 시 발생하는 중성자를 각 구성품에 따라 종류별로 분류하였다. 양성자 가속기 구성품 중 산란체에서 중성자가 가장 높게 발생되었으며 양성자의 중심선 속에서부터 멀어질수록 중성자의 선속은 감소되었다. 본 연구는 양성자 가속기의 유지 보수 및 해체에 필수적인 방사화 평가를 진행하기 위한 기초자료로 활용할 수 있을 것으로 사료된다.