• Journal of Radiation Protection and Research
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• 제11권1호
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• pp.77-82
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• 1986

Kerma와 흡수선량 사이의 관계를 결정하는 것은 선량측정의 기본적인 문제이다. 본 연구에서는 고에너지 치료용 선형가속기의 6MV X-선과 감마치료기의 $^{60}Co$에 대한 kerma와 흡수선량을 측정하였다. 본 실험결과는 $^{60}Co$감마선에 의한 물과 알루미늄의 과도 평형 영역에서의 흡수선량이 실제적으로 kerma와 일치하였으며, 최대선량 깊이는 6MV와 $^{60}Co$에서 각각 $1.45g/cm^2$과 $0.48g/cm^2$이었다. 최대 build-up에서의 흡수선량과 표면에서의 충돌 kerma의 비($K^{att}$)는 표준 조사면에서 물과 알루미늄에 대해, 6MV인 경우는 0.949, $^{60}Co$인 경우는 0.992이었다. 이 결과는 $K^{att}$의 물질에 대한 의존성이 매우 작음을 보여준다.

• Journal of Radiation Protection and Research
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• 제5권1호
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• pp.7-10
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• 1980

With the conceptual definition of the quotient(${\beta}$) of absorbed dose and the collision part of kerma for photon beams, the procedure of computing ${\beta}$ is briefly described. A series of calculations of ${\beta}$ was carried out for photons of 0.4, 0.5, 1 and 2 MeV in polystyrene, carbon, air and aluminum. Resultant values are tabulated and evaluated.

• Nuclear Engineering and Technology
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• 제56권4호
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• pp.1204-1212
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• 2024

To accurately calculate the heating distribution of the fast reactor, a neutron-photon library in MATXS format named Knight-B7.1-1968n × 94γ was processed based on the ENDF/B-VII.1 library for ultrafine groups. The neutron cross-section processing code MGGC2.0 was used to generate few-group neutron cross sections in ISOTXS format. Additionally, the self-developed photon cross-section processing code NGAMMA was utilized to generate photon libraries for neutron-photon coupled heating calculations, including photo-atom cross sections for the ISOTXS format, prompt photon production cross sections, and kinetic energy release in materials (KERMA) factors for neutrons and photons, and the self-shielding effect from the capture and fission cross sections of neutron to photon have been taken into account when the photon source generated by neutron is calculated. The interface code GSORCAL was developed to generate the photon source distribution and interface with the DIF3D code to calculate the neutron-photon coupling heating distribution of the fast reactor core. The neutron-photon coupled heating calculation route was verified using the ZPPR-9 benchmark and the RBEC-M benchmark, and the results of the coupled heating calculations were analyzed in comparison with those obtained from the Monte Carlo code MCNP. The calculations show that the library was accurately processed, and the results of the fast reactor neutron-photon coupled heating calculations agree well with those obtained from MCNP.

• Nuclear Engineering and Technology
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• 제56권2호
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• pp.673-684
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• 2024

STREAM, developed by the Computational Reactor Physics and Experiment laboratory (CORE) of the Ulsan National Institute of Science and Technology (UNIST), is a deterministic neutron- and photon-transport code primarily designed for light water reactor (LWR) analysis. Initially, the photon module in STREAM did not account for fluorescence and bremsstrahlung photons. This article presents recent developments regarding the integration of atomic relaxation and bremsstrahlung models into the existing photon module, thus allowing for the transport of secondary photons. The photon flux and photon heating computed with the newly incorporated models is compared to results obtained with the Monte Carlo code MCS. The incorporation of secondary photons has substantially improved the accuracy of photon flux calculations, particularly in scenarios involving strong gamma emitters. However, it is essential to note that despite the consideration of secondary photon sources, there is no noticeable improvement in the photon heating for LWR problems when compared to the photon heating obtained with the previous version of STREAM.

• 한국의학물리학회:학술대회논문집
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• 한국의학물리학회 2002년도 Proceedings
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• pp.241-243
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• 2002

New types of protocols have been recently in development, all based on an absorbed dose-to-water with the aim of improving the accuracy of measurements of absorbed dose to water. IAEA TRS-277, the air-kerma standard-based present protocol, and IAEA TRS-398 and AAPM TG-51, the absorbed dose-to-water standard-based new one, were studied and compared theoretically and experimentally for photon beams of 6, 10, and 15 MV. NE 2571 and 3 Farmer types of ionization chambers in widely commercial use were used to determine an absorbed dose to water at the reference depth in water. Two different kinds of calibration factors were given respectively for every chamber calibrated in $\^$60/CO gamma ray beams from a Korean Secondary Standard Dosimetry Laboratory (KFDA). This work shows that there is around 1 % of difference of absorbed doses measured between two different types of calibration systems owing to different physical parameters and reference conditions used. We hope this work to help form the basis on development of new type of protocol in Korea.

• Nuclear Engineering and Technology
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• 제54권7호
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• pp.2670-2689
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• 2022

STREAM - a lattice transport calculation code with method of characteristics for the purpose of light water reactor analysis - has been developed by the Computational Reactor Physics and Experiment laboratory (CORE) of the Ulsan National Institute of Science and Technology (UNIST). Recently, efforts have been taken to develop a photon module in STREAM to assess photon heating and the influence of gamma photon transport on power distributions, as only neutron transport was considered in previous STREAM versions. A multi-group photon library is produced for STREAM based on the ENDF/B-VII.1 library with the use of the library-processing code NJOY. The developed photon solver for the computation of 2D and 3D distributions of photon flux and energy deposition is based on the method of characteristics like the neutron solver. The photon library and photon module produced and implemented for STREAM are verified on VERA pin and assembly problems by comparison with the Monte Carlo code MCS - also developed at UNIST. A short analysis of the impact of photon transport during depletion and thermal hydraulics feedback is presented for a 2D core also from the VERA benchmark.

• Asian Pacific Journal of Cancer Prevention
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• 제17권1호
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• pp.153-157
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• 2016

Background: In radiation therapy, estimation of surface doses is clinically important. This study aimed to obtain an analytical relationship to determine the skin surface dose, kerma and the depth of maximum dose, with energies of 6 and 18 megavoltage (MV). Materials and Methods: To obtain the dose on the surface of skin, using the relationship between dose and kerma and solving differential equations governing the two quantities, a general relationship of dose changes relative to the depth was obtained. By dosimetry all the standard square fields of $5cm{\times}5cm$ to $40cm{\times}40cm$, an equation similar to response to differential equations of the dose and kerma were fitted on the measurements for any field size and energy. Applying two conditions: a) equality of the area under dose distribution and kerma changes in versus depth in 6 and 18 MV, b) equality of the kerma and dose at $x=d_{max}$ and using these results, coefficients of the obtained analytical relationship were determined. By putting the depth of zero in the relation, amount of PDD and kerma on the surface of the skin, could be obtained. Results: Using the MATLAB software, an exponential binomial function with R-Square >0.9953 was determined for any field size and depth in two energy modes 6 and 18MV, the surface PDD and kerma was obtained and both of them increase due to the increase of the field, but they reduce due to increased energy and from the obtained relation, depth of maximum dose can be determined. Conclusions: Using this analytical formula, one can find the skin surface dose, kerma and thickness of the buildup region.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1996년도 춘계학술발표회논문집(4)
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• pp.34-39
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• 1996

A series of measurements was peformed between KAERI and PNNL, U.S.A at KAERI secondary calibration laboratory to intercompare and verify the KAERI reference photon radiation fields by using air equivalent plastic walled ionization chambers, Different ionization chambers of two laboratories were used to determine the air kerma rate, free-in-air, at reference positions in the KAERI photon radiation fields, As the results, the agreement in the cross measurements between two laboratories was found to be within less than ${\pm}$ 3 %. This degree of consistency was considered to be encouraging, because each laboratory maintains independently its calibration traceablity with its national primary standard

• Journal of Radiation Protection and Research
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• 제23권1호
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• pp.33-47
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• 1998

한국원자력연구소 교정시설에 설치되어 있는 MG325 X-선 발생장치와 ISO-4037에서 제시하고 있는 라디에이티 및 필터 8종을 조합하여 8.6 keV 부터 75 keV 까지의 단일에너지 형광 X-선을 제작하였다. 1차 X-선에 의하여 라디에이터에서 발생된 형광 X-선중 $K_{\beta}$를 필터를 사용하여 제거한 후 단지 $K_{\alpha}$만의 형광 X-선 스펙트럼을 고순도 평판형 반도체검출기와 휴대용 다중파고분석기로 분석하였으며 35 cc 전리함을 이용하여 이때의 선량률 (air kerma rates)를 측정하여 계산결과와 비교하였다. 또한 방사선장의 균일도분포를 전리함과 사진현상을 통하여 결정하였으며 산란 X-선의 영향도 측정하여 실제 적용가능성을 검토하였다. 실험결과 순도가 90 % 이상되는 8.6 keV부터 75 keV까지의 단일에너지 형광 X-선을 얻었으며 라디에이터 중심으로부터 43 cm 위치에서의 선량률은 1.91 mGy/h (라디에이터 : Au, 필터 : W)로부터 54.2mGy(라디에이터 : Mo, 필터 : Zr) 까지였다. 선량률 측정지점에서 방사선장의 유효면적은 12 cm ${\times}$ 12 cm로 계측기의 교정이나 개인선량계의 조사에 전혀 문제가 없음을 확인하였고 산란방사선의 영향도 3% 이하였다.

• Journal of Radiation Protection and Research
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• 제21권4호
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• pp.255-262
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• 1996

이 논문은 최근 한국원자력연구소(KAERI)와 미국 패시픽노스웨스트 국립연구소(일명, 바텔연구소, PNNL)이 개인선량계의 성능검사를 위한 미국 ANSI N13.11 기준에 근거하여 KAERI 방사선 측정/교정실험실에서 수행한 KAERI 기준 광자 및 베타 방사선장의 국제 상호비교 측정결과를 설명하고 있다. 두 기관이 각각 자국의 일차 표준에 소급성을 갖는 방사선 검출기와 방사선 측정장치를 사용하여 자유공기중에서 광자의 조사선량(율), 공기커마(율)와 베타선의 절대 흡수선량(율)을 측정한 결과, 광자선장에 대해서는 ${\pm}2.0%$을 베타선장에 대해서는${\pm}1.0%$의 오차범위 내에서 잘 일치하였다. 따라서 KAERI의 기준 광자 및 베타 방사선장은 국제표준에 잘 만족되고 있음이 입증되었으며 장차 방사선 도시메트리 연구개발의 국가 기술기반으로 활용될 수 있음이 확인되었다