• Nuclear Engineering and Technology
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• v.33 no.3
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• pp.349-354
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• 2001

While the United Nations UN) agencies work to restrict the manufacture, sale, and use of land-mines worldwide, a massive clean-up effort is needed to find and destroy the estimated 100 million land-mines still buried around the world. Land-mines left behind from wars worldwide are one of the past century＇s main unsolved problems of war and remain the focus of humanitarian land-mine detection and removal primarily in Europe, Africa, Asia and Central and South America. For example, approximately 1 million anti-personnel mines and other various kinds which have been buried in the 249.4 km (155 miles) demilitarized zone (DMZ) of the Korean peninsular should be completely removed in historical process of the peaceful unification between South and North Korea. In this regard, the current trends of technologies linked to land-mine detection systems are surveyed.

• Journal of Radiation Protection and Research
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• v.26 no.3
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• pp.243-248
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• 2001

Neutron reference fields of Korea Atomic Energy Research Institute (KAERI) for calibrating neutron measuring devices to be used in radiation workplace monitoring consist of two kinds of neutron spectra, the direct and the scattered neutron fields, which are produced by using radionuclide neutron sources, 252Cf and 241AmBe sources. Necessary parameters for calibration such as the anisotropy factor of each neutron source and the room-scattered fraction of some neutron surveymeters in the KAERI calibration facility were determined by calculation or measurement. Spectral measurement of scattered neutron fields were performed at each reference calibration point using a Bonner Multi-sphere Spectrometer (BMS) and the dosimetric quantities for calibration also estimated from the neutron energy spectra which were unfolded using the BUNKI code.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.746-751
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• 1998

붕소 중성자 포획 요법(BNCT, Boron Neutron Capture Therapy)용 열외중성자빔의 개발을 위하여 방사성 동위원소인 Cf-252를 중성자 선원으로 사용하였으며 상대적으로 낮은 중성자속을 높이기 위하여 미임계 증배 집합체를 이용하였다. 이전에 계시된 미임계 증배 집합체는 높은 핵연료 농축도를 필요로 하는 단점이 있어 본 연구에서는 이를 감소시키기 위한 몇 가지 설계안을 제시하였다. 중성자빔 설계를 위하여 몬테칼로 방법을 이용한 전산코드인 MCNP를 이용, 타원형두뇌 팬텀 내에서 AD, AR ADDR및 각각의 선량성분 등을 계산함으로써 설계된 중성자빔의 특성분석을 수행하였다. 새롭게 개선되어 제시된 중성자빔의 설계는 상대적으로 낮은 핵연료 농측도를 보이면서 기존의 결과와 유사한 결과를 보여주고 있으며 특히 두뇌 팬텀 내에서의 선량률은 기존에 비해 매우 높은 값을 보임으로써 짧은 시간에 효과적으로 뇌종양을 치료할 수 있는 이 점이 있다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2005.06a
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• pp.344-349
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• 2005

Neutron count rate measurements to assay fissile content of uranium powder have been carried out in a neutron counter. The induced fission neutrons by Cf-252 neutron source are counted as the variation of fissile material in fuel material. The measured counts are compared with equivalent results obtained from calculation. It shows that the measured neutron counts versus quantity of $UO_2$ powder enrichment agreed reasonably well with the calculated values.

• Nuclear Engineering and Technology
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• v.49 no.6
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• pp.1354-1357
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• 2017

Characterization of special nuclear material may be performed using energy spectroscopy of either the neutron or gamma-ray emissions from the sample. Gamma-ray spectroscopy can be performed relatively easily using high-resolution semiconductors such as high-purity germanium. Neutron spectroscopy, by contrast, is a complex inverse problem. Here, results are presented for $^{252}Cf$ and PuBe energy spectra unfolded using a single EJ309 organic scintillator; excellent agreement is observed with the reference spectra. Neutron energy spectroscopy is also possible using a two-plane detector array, whereby time-of-flight kinematics can be used. With this system, energy spectra can also be obtained as a function of position. Spatial-dependent energy spectra are presented for neutron and gamma-ray sources that are in excellent agreement with expectations.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.11b
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• pp.655-662
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• 1996

기술적으로는 다짐장비의 개선으로 성토다짐의 시공속도가 매우 빨라지고 있으나 국내에서 적용하고 있는 현장다짐 밀도 및 수분함량 측정 방법(KS F 2311 KS F 2306)$^{(1)}$ 은 신속한 측정을 어렵게 하고 있다. 본 연구는 외국에서 개발 현재 활발히 적용되고있는 방사성동위원소를 이용한 함수량측정기개발의 시작단계로 기본설계 결정을 목적으로 한다. 함수량 측정 RI계기의 원리를 먼저 살펴본 후 실험실 내에서 자연건조된 성토용 흙으로 다짐을 하여 공시체를 제작한 뒤, 실험실용 함수량측정 RI계기를 공시체위에 놓고 폴리에틸렌과 중성자 검출기의 개수를 변화시켜가며 일정시간동안 측정개수를 측정한 값을 분석한 결과 목표측정 시간을 1분으로 하였을 때 신뢰측정개수인 10,000개이상을 계측하면서도 경제적으로 최소인 중성자검출기의 개수는 2개, 폴리에틸렌의 두께는 7cm로 결정되었다.

• Nuclear Engineering and Technology
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• v.54 no.4
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• pp.1406-1413
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• 2022

In this study, a diamond-based neutron scatter camera (DNSC) was developed for neutron spectroscopy in high flux environments. The DNSC was evaluated experimentally and through simulations. It was simulated using several Monte Carlo codes in a two-array layout. The two-array model included two diamond detectors. The simulation reconstructed the spectra of ²⁵²Cf and ²³⁹Pu-Be neutron sources with high accuracy (~93%). The two-diamond array system was experimentally evaluated, demonstrating the neutron spectroscopy capabilities of the DNSC. The reconstructed spectrum of the ²³⁹Pu-Be source manifested the characteristic peaks of the source. The advantage of a DNSC over a NSC is its ability to define any neutron double-scattering events without the need to absorb incident neutrons in the second detector, and atomic recoil energy information is not needed to determine the incident neutron energy.

• Journal of Radiation Industry
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• v.17 no.1
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• pp.119-125
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• 2023

Burnup of spent nuclear fuel should be determined accurately for the safety storage of spent nuclear fuel. In this study, a gamma detection system was developed as a part of basic research to measure the burnup of spent nuclear fuel, and its performance was evaluated using a calibration source. The prototype of the gamma detection system was based on a semiconductor sensor using a CZT (Cadmium Zinc Telluride). For quantitative evaluation, tests were conducted using ¹³⁷Cs, ¹³⁴Cs and ²⁵²Cf calibration source. In the performance evaluation, Its field applicability was verified by assessing the energy resolution, the detection linearity and the shielding attenuation according to the nuclide.

• Weed & Turfgrass Science
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• v.3 no.3
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• pp.246-252
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• 2014

This study was conducted to evaluate the effects of two amino acid fertilizers on the growth of creeping bentgrass and N uptake. Fertilizer treatments were designed as follows; non-fertilizer (NF), control (CF), recommended amount (ALF), double amount (2ALF) of amino acid liquid fertilizer (AaLF), recommended amount (ASLF) and double amount (2ASLF) of amino acid liquid fertilizer contained with saponin (AaSLF). Turf quality of treatments of AaLF and AaSLF such as turf color index, chlorophyll index and root length was similar to the treatment of CF. Dry weight and content, uptake and availability of N were investigated highest in the 2ALF and 2ASLF. These results suggested that foliar application of AaLF and AaSLF was enhanced turf quality and growth of creeping bentgrass by stimulating uptake and availability of N.

• Journal of The Korean Society of Grassland and Forage Science
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• v.11 no.4
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• pp.252-257
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• 1991

In a two-year's field experiment, the effectiveness of magnesium-and boron-enriched complex fertilizer (CF, N-P$_2$O$_{5}$-K$_2$O-MgO-B$_2$O$_3$: 14-10-12-3-0.2) on the maintenance and management of hilly pasture was studied. The effects of CF and some straight fertilizers (SF) on forage yields, yield components, and chemical compositions were compared in a mixed grass-clover (orchardgrass, tall fescue, kentucky bluegrass, and ladino clover) and a pure grass (orchardgrass) swards. The results are summarized as follows: 1. Considerably higher average dry matter yields were obtained in the CF plots than in the SF plots. In the mixed sward, the yields of whole mixed forages were inclosed by 10.8-14.5%, grasses by 11%, and legume by 21.5-31.0% by the use of the CF over the use of SF. In the pure grass sward, the yield of grasses was increased by 7.0-21.8%. 2. The rates of yield increase due to the application of CF were dependent on such factors as types of sward (pure or mixed), application rates of NPK, and forage species. The increase of forage yields due to the CF was greater at the normal rate of NPK application than at lower application rate, and in legume forage than in grass forage. 3. The crude fiber, crude fat and NFE contents of forages were not significantly changed by different treatments. However, the forage of CF plot at the normal application rate of NPK contained relatively higher amount of crude protein and crude fat compared with the forages of other plots. 4. There were no significant differences in the contents of mineral nutrients in forages among the different treatments. In spite of the application of Mg-enriched CF, the contents of Mg in soils and forages were below the optimum level.