• 비파괴검사학회지
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• 제20권3호
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• pp.183-190
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• 2000

본 연구에서는 고속 중성자가 조사된 원자로 용기 재료의 자기적 성질 변화를 $M{\ddot{o}}ssbauer$ 분광법을 이용하여 측정하였으며, X-선 회절실험을 이용하여 중성자 조사재료의 결정성 변화를 평가하였다. 시편은 크기가 $23mm{\times}18mm{\times}70{\mu}m$로 제작되었으며, 343K에서 $10^{12}n/cm^2{\sim}10^{18}n/cm^2$의 범위에서 중성자 조사를 하였다. X-선 회절실험 결과로부터, $10^{16}n/cm^2$의 중성자가 조사된 시료에서부터 결정성이 변화가 시작되고, $10^{17}n/cm^2$ 이상의 중성자가 조사된 시료에서 결정성이 심각하게 손상되는 것이 관찰되었다. 또한 $M{\ddot{o}}ssbauer$ 분광실험으로부터 중성자 조사량이 $10^{16}n/cm^2$ 이하인 시료에서는 자기적성질의 변화가 관찰되지 않았으나, $10^{17}n/cm^2$ 이상의 중성자가 조사된 시료에서 자기완화 현상이 일어나는 것이 관찰되었다. 따라서 두 실험 모두 비파괴적 실험방법에 따른 중성자 조사취화 평가로 활용이 가능한 것으로 평가되었다.

• Nuclear Engineering and Technology
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• 제45권7호
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• pp.921-928
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• 2013

A future nuclear energy system is being developed at Korea Atomic Energy Research Institute (KAERI), the system involves a Sodium Fast Reactor (SFR) linked with the pyro-process. The pyro-process produces a source material to fabricate a SFR fuel rod. Therefore, an isotopic fissile content assay is very important for fuel rod safety and SFR economics. A new technology for an analysis of isotopic fissile content has been proposed using a lead slowing down spectrometer (LSDS). The new technology has several features for a fissile analysis from spent fuel: direct isotopic fissile assay, no background interference, and no requirement from burnup history information. Several calculations were done on the designed spectrometer geometry: detection sensitivity, neutron energy spectrum analysis, neutron fission characteristics, self shielding analysis, and neutron production mechanism. The spectrum was well organized even at low neutron energy and the threshold fission chamber was a proper choice to get prompt fast fission neutrons. The characteristic fission signature was obtained in slowing down neutron energy from each fissile isotope. Another application of LSDS is for an optimum design of the spent fuel storage, maximization of the burnup credit and provision of the burnup code correction factor. Additionally, an isotopic fissile content assay will contribute to an increase in transparency and credibility for the utilization of spent fuel nuclear material, as internationally demanded.

• Nuclear Engineering and Technology
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• 제55권10호
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• pp.3648-3658
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• 2023

The early localization of a fuel subassembly with a failed (wet rupture) fuel pin is very important in reactors to limit the associated radiological and operational consequences. This requires a fast and reliable system for failure detection and their localization in the core. In the Prototype Fast Breeder Reactor, the system specially designed for this purpose is Failed Fuel Location Modules (FFLM) housed in the control plug region. It identifies a failed sub-assembly by detecting the presence of delayed neutrons in the sodium from a failed sub-assembly. During the commissioning phase of PFBR, it is mandatory to demonstrate the FFLM effectiveness. The paper highlights the engineering and physics design aspects of FFLM and the integrated simulation towards its function demonstration with a source assembly containing a perforated metallic fuel pin. This test pin mimics a MOX pin of 1 cm² of geometrical defect area. At 10% power and 20% sodium flow rate, the counts rate in the BCCs of FFLM system range from 75 cps to 145 cps depending upon the position of DN source assembly. The model developed for the counts simulation is applicable to both metal and MOX pins with proper values of k-factor and escape coefficient.

• 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.

• Nuclear Engineering and Technology
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• 제52권10호
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• pp.2306-2312
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• 2020

Here we report on the first results of sensitivity evaluation of the gadolinium-aluminum-gallium- garnet (GAGG) scintillation detector with SiPM readout to fast and slow neutrons and, to the natural background and Co-60 γ-radiation as well. Data on sensitivity were obtained using certified dosimetry benches, so it can be utilized in the calculation of detection limits of neutron flux with such type of detectors. It was concluded that use of GAGG scintillator has a good prospect for neutron monitoring in different parts of nuclear research reactors and power plants.

• 전기의세계
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• 제29권2호
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• pp.118-128
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• 1980

The properties of plasmas produced by high power glass laser were investigated with various methods of diagnostics. Electron temperature was estimated by measurement of soft X-ray, and ion temperature was estimated by measurement of the time-of-flight of ion. The measurement of incident and reflected laser light, and Schlieren and shadowgragh methods were also used. No influence of laser pulse duration on the temperature was observed in the case of durations 2, 4 and 10 nsecs. The effective heating of plasma occurred in about 2 nsec of beginning of incident laser pulse. The experimental results for fast rising laser pulse were discussed and the influence of resetime of laser pulse on the heating of plasma was described. Neutrons produced by irradiating laser beam to solid deuterium target were detected.

• Nuclear Engineering and Technology
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• 제53권7호
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• pp.2075-2083
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• 2021

The article provides a review of the research results obtained during of more than 20 years concerning using the gaseous radiochemical method (GRCM) for detecting of ionizing radiation. This method based on threshold nuclear reactions with production of radioactive noble gas which does not interact with the materials of gaseous tract. The applications of GRCM in the diagnostics of neutrinos, neutrons, charged particles, thermonuclear plasma thermometry, and the study of the structure and dynamics of astrophysical objects, position-sensitive dosimetry of neutron targets with accelerator driving, spatial distribution of the fast neutron flux density in a nuclear reactor allowing the transformation of longitudinal coordinate of neutron flux distribution into a temporal distribution of the radiochemical gas decay counting rate ("barcode" semblance) and measurement of bombarding particles spectra are described. Experimental testing of the described technologies was made on the neutron target driven with the linear proton accelerator of Institute for Nuclear Research of Russian Academy of Sciences (INR RAS).

• Nuclear Engineering and Technology
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• 제51권3호
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• pp.784-791
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• 2019

In the present study, a series of tungsten austenitic stainless steel alloys have been developed by interchanging the molybdenum in standard SS316 by tungsten. This was done to minimize the long-life residual activation occurred in molybdenum and nickel after decommissioning of the power plant. The microstructure and mechanical properties of the prepared alloys are determined. For the sake of increasing multifunction property of such series of tungsten-based austenitic stainless steel alloys, gamma shielding properties were studied experimentally by means of NaI(Tl) detector and theoretically calculated by using the XCOM program. Moreover, fast neutrons macroscopic removal cross-section been calculated. The obtained combined mechanical, structural and shielding properties indicated that the modified austenitic stainless steel sample containing 1.79% tungsten and 0.64% molybdenum has preferable properties among all other investigated samples in comparison with the standard SS316. These properties nominate this new composition in several nuclear application domains such as, nuclear shielding domain.

• 대한수의학회지
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• 제41권2호
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• pp.203-210
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• 2001

방사선 피폭선량의 예측을 위한 방사선 민감 지표 모델 개발을 위하여 코발트-60 감마선과 의료용 싸이크로트론 50 MeV($p{\to}RBe^+$) fast neutron을 0.25 Gy에서 1 Gy의 선량을 랫드에 각각 전신 조사한 후 말초혈액내 임파구와 소장에 음와세포의 형태학적 변화를 apoptotic fragment assay법을 이용하여 관찰하였다. 모든 방사선조사군에서 음와세포와 말초 임파구에 아포토시스의 유도가 증가된 것이 관찰되었으며, 이것은 방사선이 방사선 민감세포의 아포토시스 유도를 자극한 것으로 보인다. 상기의 결과는 아포토시스가 손상된 세포를 제거하므로 손상된 방사선 민감 표적 장기의 항상성 유지에 중요한 역할을 하는 것으로 판단되었다. Apoptotic fragments의 발생빈도에 대한 선량-반응곡선에 있어서 음와세포는 중선자 조사군이 $y=0.3+(6.512{\pm}0.279)D(r^2=0.975)$으로, 반면에 감마선 조사군은 $y=0.3+(4.435{\pm}0.473)D+(-1.300{\pm}0.551)D^2(r^2=0.988)$의 식을 얻었다. 그리고 말초 임파구에서는 감마조사군이 $y=3.5+(118.410{\pm}10.325)D+(-33.548{\pm}12.023)D^2(r^2=0.992)$의 식으로 나타났다. 이와 같이 감마선조사군은 공히 linear quadratic model 이였으나 중성자조사군은 linear model 로 관찰되었다. 조사된 세포의 종류와 상관없이 apoptotic fragments의 발생빈도와 조사 선량간의 유의한 효과가 있는 것으로 확인되었다. 이상의 결과에서 조사선량의 증가와 비례하여 방사선 민감 세포의 apoptotic fragments가 수적으로 증가하였으며, 고준위 방사선이 저준위 방사선보다 선량 반응 곡선과 시간 경과에 따른 영향이 보다 강한 것으로 인지되었으며, 음와세포의 apoptosis 유도에 대한 중성자선의 방사선 생물학적 효과비(RBE)는 1.919 였다. 그리고 모든 방사선조사군에서 방사선피폭 후 4시간과 6시간에 apoptosis 유도가 가장 많았으며, 음와세포의 형태학적 소견은 정상 대조군에서 관찰되지 않는 전형적인 apoptotic fragments가 나타났다. 따라서 음와 세포와 말초 임파구에서의 아포토시스 유도는 방사선 조사에 의한 세포 손상의 생물학적 영향 평가를 위한 검색 및 방사선 피폭선량 예측의 지표로 이용 가능할 것으로 사료됨.

• Nuclear Engineering and Technology
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• 제27권1호
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• pp.74-83
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• 1995

원자로 압력용기에서의 정화한 속중성자 조사량의 계산은 발전소 압력용기 surveillance program의 핵심적인 부문이다. 최근 기존의 ENDF /B-III~V에 있는 철의 핵단면적 자료가 압력용기와 같은 철이 포함된 구조물에서 속중성자속을 낮게 평가하는 것으로 알려지고 있다. 본 논문에서는 ENDF /B-IV와 VI의 철(Fe) 자료의 비교를 위해 영광3/4호기 모델과 2개의 ENDF/B 파일에 있는 각각의 철자료를 이용하여 47-에너지그룹 핵단면적집 (CXFe-IV와 CXFe-VI )을 만들었다. CXFe-IV와 CXFe-VI를 사용하여 수행한 DOT4.3 계산결과에 의하면 압력용기 취화해석에 중요한 속중성자속(E 〉 1.0 MeV) 계산에서 ENDF /B-VI의 철자료를 사용한 경우가 ENDF /B-IV의 철자료를 사용한 경우보다 압력용기 내부표면에서 7.6%, 외부표면에서 20% 높게 나타났다.