• Nuclear Engineering and Technology
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• 제51권4호
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• pp.1075-1080
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• 2019

This paper presents a study on thermal neutron reflection properties of neutron guide for cylinder, spindle, elliptic and parabolic geometries using $^{241}Am-Be$ neutron source (5.2 Ci) and $BF_3$ detector, whereas neutron guide is important instrument for transportation of neutrons. To this goal, the required inner and outer radii of neutron guide have been calculated to achieve the highest guided thermal neutron flux based on MCNPX Monte Carlo code. The maximum flux of cylinder geometry with a length 50 cm has been obtained at an inner radius 9 cm and an outer radius 21 cm. Also, the maximum value of thermal neutron albedo is $0.46{\pm}0.001$ at 12 cm thickness of parabolic guide.

• Journal of Radiation Protection and Research
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• 제26권3호
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• pp.167-175
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• 2001

Semiconductor diode detectors coated with neutron reactive material are presently under investigation for various uses, such as remote sensing of thermal neutrons, fast neutron counting, and thermal neutron radiography. Theory indicates that single-coated devices can yield thermal neutron efficiencies from 4% to 11 %, which is supported by experimental evidence. Radiation endurance measurements indicate that the devices function well up to a limiting thermal neutron fluence of $10^{13}/cm^2$, beyond which noticeable degradation occurs. Thermal neutron contrast images of step wedges and simple phantoms, taken with dual in-line pixel devices, show promise for thermal neutron imaging detectors.

• 한국산림과학회지
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• 제17권1호
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• pp.1-15
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• 1973

돌연변이수발(突然變異誘發)에 의(依)한 방법(方法)으로 중요조림수종(重要造林樹種)의 품종(品種)을 개량(改良)코자 Robinia pseudoacacia, Pinus densiflora, Pinus rigida, Pinus thunbergii 및 Larix leptolepis의 종자(種子)를 미국(美國) Brookhaven National Laboratory에 송부(送付)하여 X-ray와 thermal neutron를 조사처리(照射處理)하고 상기종자(上記種子)들의 발아율(發芽率)을 조사(調査)하는 한편 조사처리(照射處理)된 종자(種子)에서 얻어진 아까시나무 유묘(幼苗)의 몇몇 특성(特性)을 조사(調査)하였다. 1. Thermal neutron 3시간(時間)~9시간(時間) 조사처리(照射處理) 범위(範圍)에 있어서 조사처리시간(照射處理時間)의 증가(增加)에 따라 Robinia pseudoacacia, Pinus densiflora, Pinus thunbergii 및 Pinus rigida 종자(種子)의 발아율(發芽率)이 감소(減少) 되었으며 특(特)히 Larix leptolepis의 종자(種子)는 이와 같은 선량범위내(線量範圍內)에서 완전(完全) 치사(致死)하였다. 2. X-ray 10,000r~30,000r 범위(範圍)의 조사처리(照射處理)는 Pinus densiflora, Robinia pseudoacacia, Pinus rigida 종자(種子)의 발아율(發芽率)을 대단조해(大端阻害) 저하(低下)시켰고 특(特)히 Pinus thunbergii와 Larix leptolepis의 종자(種子)는 거의 치사(致死)케하였다. 3. 조사처리(照射處理)된 아까시나무의 생장상황(生長狀況)은 X-ray 및 thermal neutron 조사처리(照射處理)에 있어 선량(線量)의 증가(增加)에 따라 모두 생육(生育)이 저하(低下)되었으나 thermal neutron으로 3시간(時間) 조사처리(照射處理)된 개체(個體)들은 비교목(比較木)에 비(比)하여 14.9% 생육증가(生育增加)를 보였으며 또한 가시없는 개체(個體)가 상당(相當)히 출현(出現)되었다. 4. 조사처리(照射處理)된 아까시나무의 형태적(形態的) 변이(變異)에 있어서는 X-ray 및 thermal neutron 조사처리(照射處理)에 있어서 엽반입개체(葉搬入個體), 엽부정형개체(葉不整形個體), 백자개체(白子個體), 등(等)이 출현(出現)되었다. 5. Thermal neutron으로 조사처리(照射處理)된 아까시나무는 정상적(正常的)인 체세포분열(體細胞分裂)이 대부분(大部分)이나 비정상적(非正常的)인 세포분열(細胞分裂), 이핵세포(二核細胞), 이인세포(二仁細胞) 및 염색체괴(染色體塊) 등(等)을 관찰(觀察)할 수 있었다. 6. X-ray 및 thermal neutron 조사처리(照射處理)된 아까시나무의 pawdery mildew에 대(對)한 저항성(抵抗性)은 선량증가(線量增加)에 따라 감소(減少)되었다. 7. Thermal neutron 조사처리(照射處理)된 아까시나무의 기공장(氣孔長)은 비교목(比較木)과 대차(大差)가 없었고 단위면적당기공수(單位面積當氣孔數)는 처리목(處理木)이 감소(減少)되었다. 또한 엽전체(葉全體)의 후(厚) 및 엽표층(葉 表層)의 후(厚)는 thermal neutron 조사처리목(照射處理木)이 비교목(比較木)에 비(比)하여 증가(增加)되었으며 붕상조직(棚狀組織)의 폭(幅)은 비교목(比較木)보다 감소(減少)되었다.

• Nuclear Engineering and Technology
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• 제54권7호
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• pp.2572-2578
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• 2022

An approximate method for calculating the cadmium ratio of a cyclotron-based thermal neutron radiography system was developed. In this method, the Monte-Carlo code, MCNP6.2, was employed to calculate the neutron capture rates of Au-197, and the cadmium ratio was obtained by computing the ratio of neutron capture rates. From the simulation results, the computed cadmium ratio is reasonably acceptable, and the assumption of ignoring the fast neutron contribution to the cadmium ratio is valid.

• 분석과학
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• 제16권5호
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• pp.426-429
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• 2003

Neutron induced prompt gamma-ray spectroscopy (NIPS) system equipped with a $^{252}Cf$ neutron source and a n-type coaxial HPGe detector was installed for the quantitative analysis of aqueous samples in KAERI, Korea. Since the thermal neutron flux for the $^{252}Cf$ neutron source is relatively low compared to that for the reactor, the use of a thermal neutron reflector in the NIPS system may lead to improved results. The enhancement by using various reflectors was carried out by comparing the Cl peak with or without a cadmium plate between sample and the $^{252}Cf$ source. The use of pyrolitic graphite as a reflector provided a good result.

• Journal of Radiation Protection and Research
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• 제37권1호
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• pp.35-40
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• 2012

국내 교정기관 또는 표준기관은 중성자 검출기의 교정을 위해 비감속 및 중수감속 $^{252}Cf$ 선원과 $^{241}AmBe$ 선원을 사용하고 있다. 이런 선원들로 교정된 중성자 검출기를 이용하여 입자가속기와 같이 속중성자가 다량 존재하는 시설을 선량평가할 때, 그 정확도가 떨어지게 된다. 그 이유는, 대부분의 중성자 검출기는 열중성자에 민감하게 반응하므로 수 MeV 이상의 에너지를 가지는 속중성자장에 대한 선량당량 반응도는 부정확하다. 또한 높은 에너지의 중성자는 열중성자보다 선량기여정도가 훨씬 크기 때문이다. 이와 같은 이유로, 기존의 교정용 기준 중성자장이 아닌 수 MeV 이상의 속중성자가 존재하는 중성자장에서도 검출기를 교정할 필요가 있다. DT 중성자 발생기, 흑연집합체 그리고 폴리에틸렌 중성자 집속체를 사용하여 속중성자의 선속분율이 서로 다른 중성자장을 제작하였고, 이 중성자장에서 중성자 검출기의 선량당량 반응도를 측정하였다. 시험결과에 의하면, 속중성자 선속분율과 중성자 검출기의 종류에 따라 중성자 검출기의 반응도는 많은 차이를 보였다. 이러한 반응도 차이는 선량당량의 과대 및 과소평가를 의미하므로, 검출기가 사용되는 시설환경과 유사한 중성자장에서 반응도 교정이 필요함을 확인하였다.

• 한국방사선학회논문지
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• 제3권3호
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• pp.23-25
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• 2009

Gd-157 material has very large neutron capture cross section in the thermal region. So it is very useful to shield material for thermal neutrons. Futhermore, in the neutron capture experiment and calculation, the neutron absorption and scattering are very important. Especially these effects are conspicuous in the resonance energy region and below the thermal energy region. In the case of very narrow resonance, the effect of scattering is to be more considerable factor. In the present study, we obtained energy dependent neutron absorption ratios of natural indium in energy region from 0.003 to 100 keV by MCNP-4B Code. The coefficients for neutron absorption was calculated for circular type and 1 mm thickness. In the lower energy region, neutron absorption is larger than higher region, because of large capture cross section (1/v). Furthermore it seems very different neutron absorption in the large resonance energy region. These results are very useful to decide the thickness of sample and shielding materials.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2003년도 학술회의 논문집 정보 및 제어부문 B
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• pp.789-792
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• 2003

pMOSFET having 10 ${\mu}um$ thickness Gd layer has been tested to be used as a slow neutron sensor. The total thermal neutron cross section for the Gd is 47,000 barns and the cross section value drops rapidly with increasing neutron energy. When slow neutrons are incident to the Gd layer, the conversion electrons are emitted by the neutron absorption process. The conversion electrons generate electron-hole pairs in the $SiO_2$ layer of the pMOSFET. The holes are easily trapped in Oxide and act as positive charge centers in the $SiO_2$ layer. Due to the induced positive charges, the threshold turn-on voltage of the pMOSFET is changed. We have found that the voltage change is proportional to the accumulated slow neutron dose, therefore the pMOSFET having a Gd nuclear reaction layer can be used for a slow neutron dosimeter. The Gd-pMOSFET were tested at HANARO neutron beam port and $^{60}CO$ irradiation facility to investigate slow neutron response and gamma response respectively. Also the pMOSFET without Gd layer were tested at same conditions to compare the characteristics to the Gd-pMOSFET. From the result, we have concluded that the Gd-pMOSFET is very sensitive to the slow neutron and can be used as a slow neutron dosimeter. It can also be used in a mixed radiation field by subtracting the voltage change value of a pMOSFET without Gd from the value of the Gd-pMOSFET.

• Nuclear Engineering and Technology
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• 제54권11호
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• pp.4226-4230
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• 2022

The Korea Atomic Energy Research Institute (KAERI) has designed a Hybrid-Low Power Research Reactor (H-LPRR) which can be used for critical assembly and conventional research reactor as well. It is an open tank-in-pool type research reactor (Thermal Power: 50 kW_th) of which the most important applications are Neutron Activation Analysis (NAA), Radioisotope (RI) production, education and training. There are eight irradiation holes on the edge of the reactor core: IR (6 holes for RI production) and NA (2 holes for NAA) holes. In order to quantify the elemental concentration in target samples through the Instrumental Neutron Activation Analysis (INAA), it is necessary to measure neutron spectrum parameters such as thermal neutron flux, the deviation from the ideal 1/E epithermal neutron flux distribution (α), and the thermal-to-epithermal neutron flux ratio (f) for the irradiation holes. In this study, the MCNP6.1 code and FORTRAN 90 language are applied to determine the parameters for the two irradiation holes (NA-SW and NA-NW) in H-LPRR, and in particular its α and f parameters are compared to values of other research reactors. The results confirmed that the neutron irradiation holes in H-LPRR are designed to be sufficiently applied to neutron activation analysis, and its performance is comparable to that of foreign research reactors including the TRIGA MARK II.

• 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.