• Journal of Radiation Protection and Research
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• v.22 no.1
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• pp.29-33
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• 1997

Neutron room scattering corrections that should be made when neutron detectors are calibrated with a $D_2O$ moderated $^{252}Cf$ neutron source in the center of a calibration room are considered. Such room scattering corrections are dependent on specific neutron source type, detector type, calibration distance, and calibration room configuration. Room scattering corrections for the responses of a thermoluminescence dosimeter and two different types of spherical detectors to neutron source in the Radiation Calibration Laboratory(RCL) neutron calibration facility at the Korea Atomic Energy Research Institute(KAERI) were experimentally determined and are presented. The measured room scattering results are then compared with theoretical results calculated by predicting room scattering effects in terms of parameters related to the specific configuration. Agreement between measured and calculated scattering correction is generally about 10% for three kinds of detectors in the calibration facility.

• Journal of Radiation Protection and Research
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• v.10 no.1
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• pp.67-73
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• 1985

The manganous sulfate bath method for neutron source calibrations at the K-SRI is described together with the measurement of neutron emission rate of a source and the corrections applied for capture by competing nuclei of neutrons, and thermal neutron leakage, neutron absorption in the source itself. The commercially available neutron sources (Am-Be, $^{252}Cf$) for the calibration checks of neutron radiation instruments in the MeV range are considered in this paper.

• Journal of the Mineralogical Society of Korea
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• v.16 no.1
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• pp.65-73
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• 2003

In this study we have derived the two correction methods of hydrogen bonding distance. In case of the intermediate or long hydrogen bond(＞2.5 $\AA$), hydrogen bonding distances can be corrected by using the function d(O-H)=exp((2.173-d(O…O))/0.138)+0.958 obtained by least- squares fit to the data from the neutron diffraction at low temperatures. The valence-least-squares method is effective for the distance correction of very short hydrogen bond(<2.5 $\AA$). The distance correction is necessary for the long intermolecular hydrogen bond obtained from X-ray diffraction analysis.

• Nuclear Engineering and Technology
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• v.21 no.1
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• pp.12-17
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• 1989

The correction factor of neutron fraction absorbed by $^{55}$ Mn in the MnSO$_4$ bath was determined for the absolute measurement of neutron emission rate by using the solution circulation-type manganese sulfate bath system. For the determination of this correction factor, I/f, the atomic number desnsity and the effective neutron capture cross section data of Mn, S and impurity elements in the MnSO$_4$ solution were determined. For the atomic number density determination, the MnSO$_4$ solution concentration was determined by using the volumetric EDTA titration and gravimetric method. The impurity contents were analyzed by using the ICP method. For the calculation of effective neutron capture cross sections, a FORTRAN computer program EASCAL was developed in this study. in which Westcott's parameters and Axton's empirical relations are used.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.10a
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• pp.251-258
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• 1997

임계 근처에서 반응도 미터로 계단식 반응도 변화를 측정할 때는 중성자원과 감마의 영향 하에서도 정확한 반응도를 결정할 수 있으며, 중성자원과 감마를 측정할 수도 있다. 중성자원과 감마의 영향은 없으나 중성자 분포 함수만 변하는 경우에는 계산으로 예측한 분포 함수의 변화로 측정된 중성자 신호를 보정하여 반응도를 예측할 수 있다. 그러나 중성자원, 감마, 분포 함수가 복합적으로 작용하는 경우에 대하여는 이러한 방법을 적용할 수 없다. 이 매 중성자원과 감마의 영향만 있는 경우에 적용하는 방법을 쓰면 분포 함수의 변화가 측정 결과에 어떤 영향을 미치는지 분석하였다. 그 결과 분포 함수의 변화도 어느 정도 측정이 가능하며, 계산으로 예측하는 분포 함수의 변화로 측정 결과를 단순 보정하여 실제 반응도를 예측할 수 있는 것으로 나타났다.

• Proceedings of the KIEE Conference
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• 2004.07d
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• pp.2577-2579
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• 2004

중성자를 사용한 비파괴검사는 X선을 사용하는 것에 비해 상대적으로 뛰어난 투과력을 가지고 있다. 하지만 중성자와 원자핵의 반응에 의한 scattering 효과와 중성자 빔의 uniformity부족 등으로 인한 영상의 왜곡이 발생한다. 본 논문에서는 이런 중성자 영상의 왜곡을 보정하기 위한 영상처리 알고리즘을 연구하고 연구된 알고리즘을 토대로 영상처리 소프트웨어를 구현하였다. 먼저 히스토그램 연산을 이용하여 영상의 밝기와 대비를 조절하여 영상의 가시성을 높였고, 필터링 기법을 통하여 영상이 가지는 임펄스 잡음과 가우시안 잡음을 순차적으로 제거하였다. 마지막으로 가우시안 잡음 제거시 부가적으로 발생한 영상의 흐려짐을 보완하여 보다 향상된 질의 영상을 얻게 되었다. 또한 Visual C++을 사용하여 위의 알고리즘들을 GUI 환경의 프로그램으로 구현하였다.

• Journal of Radiation Protection and Research
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• v.14 no.1
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• pp.66-70
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• 1989

In routine testing, the radioactive neutron sources are particularly suitable for producing standard. neutron fields. The ISO TC-85 has proposed neutron reference radiation for the calibration of neutron measuring devices used for radiation protection purposes. Radiation laboratory of KSRI has installed a standard irradiation facility using $^{252}Cf$ and $^{241}Am-Be$ sources for calibrating personal dosimeters according to the recommendations given in ISO TC-85. In this study, correction factors for calibration related to neutron scattering and anisotropy are obtained by experiments with commercial rem meter for demonstration purposes.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2016.10a
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• pp.235-236
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• 2016

• Journal of Energy Engineering
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• v.16 no.4
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• pp.155-163
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• 2007

To insure nuclear reactor safety, the reactivity of control rods should be calculated by measuring the criticality of reactor core and it is regularly performed during the annual physics test period. Also, the core criticality should be monitored during the start-up operation to avoid reactivity induced accidents. Many research works on control rod reactivity measurement and subcriticality measurement have been accomplished throughout the world for decades and recently a new method named "Modified Neutron Source Multiplication Method (MNSM)" was proposed in Japan which is known to be improved overcoming limitations of traditional Neutron Source Multiplication Method (NSM). In this study, MNSM was tested in calculation of subcriticalities and in evaluation of application validity using the educational reactor in Kyung Hee University, AGN-201. For this study, a revised nuclear data library and a neutron transport code system TRANSX - PARTISN were established. Correction factors for various control rod positions were produced using the k-effective values and the corresponding flux distributions and adjoint flux distributions. Experimental values of the core criticality were obtained using the neutron count rates of the BF3 proportional counters. The results showed that the expected reactivity worth of control rods by MNSM agreed well with the theoretical values and the correction factors contributed much for this purpose.

• Nuclear Engineering and Technology
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• v.7 no.3
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• pp.191-198
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• 1975

A study was made on the neutron dosimetry in a mixed gamma-neutron field with LiF thermoluminescent dosimeter. In order to estimate the neutron dose in a mixed field, $^{6}$ LiF and $^{7}$ LiF dosimeters were used for fast and thermal neutron doses. The over-all conversion factors for the effects of dosimeter positions were derived for personnel monitoring and the glow curves of the LiF dosimeters for neutron and gamma-ray doses were also analyzed.