• 한국표면공학회지
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• 제52권6호
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• pp.293-297
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• 2019

Quasi-nano-hardness and corrosion behaviors of neutron-irradiated reactor pressure vessel (RPV) steels such as 15Ch2MFA (Ni<0.4, 2.520 n/㎠ (En>1.0 MeV) for 32 days. Quasi-nano-hardnesses of the 15Ch2MFA and 15Cr2NHFA steels were 183.8 and 179.8 Hv, respectively. Their corrosion rates and corrosion potentials were 2.4×10^-4Acm^-2, -515.9 mV_SHE and 6.8×10^-4 Acm^-2, -523.6 mV_SHE in NACE standard TM0284-96 solution at room temperature, respectively. 15Ch2MFA steel showed better quasi-nano-hardness and corrosion resistance than 15Cr2NHFA steel in this test condition.

• Nuclear Engineering and Technology
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• 제27권2호
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• pp.234-247
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• 1995

Trace elements in airborne particulates were analyzed by instrumental neutron activation analysis (INAA) under the optimum analytical condition. Neutron irradiation for sample was done at the irradiation hole(neutron flux 1$\times$10$^{13}$ n/$\textrm{cm}^2$.s) of TRIGA MARK-III research reactor in the Korea Atomic Energy Research Institute. For the verification of the analytical method, NIST SRM-1648 and NIES CRM No.8 ore chosen and analyzed. The accuracy and precision of the analysis of 40 and 24 trace elements in the samples were compared with the certified and reported values, respectively. The analytical method was found to be reliable enough when the analytical data of NIES sample were compared with those of different counties. In the analytical result of two or both of standard reference materials, relative standard deviation wes within the 15％ except a few elements and the relative error was within the 10％. We used this method to analyze 30 trace elements in airborne particulates collected with the high volume air sampler(PM-10) at too different locations and also confirmed the possibility to use this method as a routine monitoring tool to find out environmental pollution sources.

• 열처리공학회지
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• 제17권3호
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• pp.151-164
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• 2004

The changes of microstructural and mechanical properties were evaluated for the high burn-up fuel claddings after the neutron irradiation of $1.8{\sim}3.1{\times}10^{20}n/cm^2$ (E>1.0 MEV) in HANARO research reactor. After the irradiation, the spot-type dislocations (a-type dislocations) were easily observed in most claddings, and the density of the dislocations was different depending on the grains and was higher at grain boundaries than within grains. As the final annealing temperature increased, the density of spot-type dislocations increased and the line-type dislocations (c-type dislocations) which was perpendicular to the <0002> direction, appeared sporadically in some claddings. However, the types of precipitates in the fuel claddings after the irradiation were not changed from that in unirradiated claddings. The mechanical properties including the hardness, strength and elongation after the irradiation were changed due to the formation of spot-type dislocations. That is, the increase in hardness and strength as well as the decrease in elongation after the irradiation was occurred simultaneously with increasing the final annealing temperature. Owing to the Nb contribution to the formation of spot-type dislocation during the irradiation, the increase in hardness and strength in higher Nb-contained Zr alloys after the irradiation was higher than that in lower Nb-contained Zr alloys.

• Nuclear Engineering and Technology
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• 제49권4호
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• pp.787-791
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• 2017

Americium-beryllium (Am-Be; n, ${\gamma}$) is a neutron emitting source used in various research fields such as chemistry, physics, geology, archaeology, medicine, and environmental monitoring, as well as in the forensic sciences. It is a mobile source of neutron activity (20 Ci), yielding a small thermal neutron flux that is water moderated. The aim of this study is to develop a model to increase the neutron thermal flux of a source such as Am-Be. This study achieved multiple advantageous results: primarily, it will help us perform neutron activation analysis. Next, it will give us the opportunity to produce radio-elements with short half-lives. Am-Be single and multisource (5 sources) experiments were performed within an irradiation facility with a paraffin moderator. The resulting models mainly increase the thermal neutron flux compared to the traditional method with water moderator.

• Nuclear Engineering and Technology
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• 제53권1호
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• pp.188-198
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• 2021

A modern approach to nuclear energy involves reprocessing like transmutations of spent nuclear fuel products to reduce their radiotoxicity and time needed for their storage. For this purpose, they are immobilized in inert matrices made of zirconia and can be "burned" in fast neutron reactor or Accelerator Driven System. These matrices in spherical form can be obtained by sol-gel process. The paper presents a method of microspheres fabrication based on the combined Complex Sol-Gel Process and double extraction process consisting in the preparation of zirconium-ascorbate sol and simultaneous extraction of water and nitrates. The procedure allows obtaining gel microspheres with a diameter of 50 ㎛, which after heat treatment are processed into the final product. The synthesis of zirconia microspheres with Yttrium by internal gelation process is well known for over a decade now. However, the explanation and characterization of synthesis of such material by extraction of water process is rarely found. Parameters such as: pH, viscosity, shape, sphericity and crystal structure have been determined for synthesized products and semi-products. In addition, preliminary research consisting in irradiation of the obtained materials in fast and thermal neutron flux was carried out. The obtained results are presented and described in this work.

• 분석과학
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• 제16권6호
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• pp.443-449
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• 2003

붕산수에 대한 열중성자 (thermal neutron) 조사실험을 하나로를 이용하여 다음과 같은 세가지 조건에서 수행하였다: (A) $^{10}B$ 농도 = $203.0{\mu}g/mL$, 조사시간 = 1 시간; (B) $^{10}B$ 농도 = $381.4{\mu}g/mL$, 조사시간 = 1 시간; (C) $^{10}B$ 농도 = $381.4{\mu}g/mL$, 조사시간 = 0.5 시간. 열중성자 조사 시 발생하는 핵반응 [$^{10}B(n{\cdot}{\alpha})^7Li$]으로부터 생성된 $^7Li$의 양은 불꽃 없는 원자흡수분광분석법 (flameless atomic absorption spectroscopy)으로 측정하였다. (A), (B), (C) 실험에서 측정된 $^7Li$의 농도는 각각 0.18 (이론치 = 0.23), 0.31 (이론치 = 0.44), 0.16 (이론치 = 0.22) ${\mu}g/mL$로 이 값들은 각각 이론치의 78.3, 70.5, 71.6%에 해당한다 중성자 조사 후 붕산수의 pH는 조사 전의 값에 비하여 상당히 낮은 값을 보였다. 이는 물의 방사분해물의 영향으로 붕산수가 해리도가 큰 polyborate 형태로 전이되기 때문으로 판단된다.

• 한국자원식물학회지
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• 제18권3호
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• pp.359-366
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• 2005

재배종담배(Nicotiana tabacum L. cv.), 야생종담배 (N. plumbaginifolia)와 벼종자(Orya sativa L, cv.)에 neutron빔을 각각 조사(irradiation)하여 발아, 식물체의 생장과 DNA의 변이에 미치는 영향을 검토하였다. 담배종자와 벼종자에 90, 180, 270, 360, 450, 540 Gy까지 조사로 발아율은 크게 감소하지 않았고, 생장에 있어 유의적인 차이는 없었다. 그러나 담배식물체에서 총 200개체 중 71개체(약 $36\%$)가 잎에서 형태 이상을 나타내었다. 또한 줄기색 변이체, 엽색변이체, 화형변이체를 유도하였다. 이 결과는 neutron빔이 유용한 돌연변이원으로서 가능성이 있음을 시사해 준다. Neutron빔을 조사한 후 생장한 담배식물체의 잎에 대하여 총 34개의 primer를 이용하여 RAPD 분석한 결과 20개의 primer에서 총 104개의 DNA 단편이 증폭되었고, 중성자 빔조사처리구에서만 출현하는 DNA 단편은 나타나지 않았다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1997년도 춘계학술발표회논문집(2)
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• pp.427-432
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• 1997

Boron neutron capture therapy(BNCT) is a binary treatment modality that can selectively irradiate tumor tissue. More is known now about the radiation biology of BNCT, which has reemerged as a potentially useful method for preferential irradiation of tumors. We design a square reactor (that can easily be reconfigured into polygonal reactors as the need arises) with four slab type assemblies to produce high quality epithermal neutron beans and thermal neutron beams jot use in neutron capture therapy. With a low operating power of 300kW, the heat generated in the core can be removed by natural convection through a pool of tight water. The proposed design in this study could be constructed for a dedicated clinical BNCT facility that would operate very safely.

• 한국자기학회:학술대회 개요집
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• 한국자기학회 2000년도 춘계연구발표회 논문개요집
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• pp.86-87
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• 2000

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2018년도 추계학술논문요약집
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• pp.549-550
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• 2018