• Nuclear Engineering and Technology
• /
• 제49권1호
• /
• pp.189-195
• /
• 2017

Gel dosimeters have unique advantages in comparison with other dosimeters. Until now, these gels have been used in different radiotherapy techniques as a reliable dosimetric tool. Because dose distribution measurement is an important factor for appropriate treatment planning in different radiotherapy techniques, in this study, we evaluated the ability of the N-isopropylacrylamide (NIPAM) polymer gel to record the dose distribution resulting from the mixed neutron-gamma field of boron neutron capture therapy (BNCT). In this regard, a head phantom containing NIPAM gel was irradiated using the Tehran Research Reactor BNCT beam line, and then by a magnetic resonance scanner. Eventually, the $R_2$ maps were obtained in different slices of the phantom by analyzing T2-weighted images. The results show that NIPAM gel has a suitable potential for recording three-dimensional dose distribution in mixed neutron-gamma field dosimetry.

• 대한전기학회논문지:전기물성ㆍ응용부문C
• /
• 제52권12호
• /
• pp.545-552
• /
• 2003

When a Si PIN diode is exposed to fast neutrons, it results in displacement damage to the Si lattice structure of the diode. Defects induced from structural dislocation become effective recombination centers for carriers which pass through the base of a PIN diode. Hence, increasing the resistivity of the diode decreases the current for the applied forward voltage. This paper involves the development of a neutron sensor based on the phenomena of the displacement effect damaged by neutron exposure. The neutron effect on the semiconductor was analyzed. Several PIN diode arrays with various thickness and cross-section area of the intrinsic layer(I layer) were fabricated. Under irradiation tests with a neutron beam, the manufactured diodes have a good linearity to neutron dose and show that the increase of thickness of I layer and the decrease of cross-section of PIN diodes improve the sensitivity. Newly developed PIN diodes with thicker I layer and various cross section, were retested and then showed the best neutron sensitivity at the condition that the I layer thickness was similar to a side length. On the basis of two test results, final discrete PIN diodes with a rectangular shape were manufactured and the characteristics as neutron detectors were analyzed through the neutron beam test using on-line electronic dosimetry system. Developed PIN diode shows a good linearity as dosimetry in the range of 0 to 1,000cGy(Tissue) and its neutron sensitivity is 13mV/cGy at constant current of 5mA, that is three times higher than that of commercially available neutron detectors. And the device shows little dependency on the orientation of the neutron beam and a considerable stability in annealing test for a long period.

• Journal of Radiation Protection and Research
• /
• 제32권4호
• /
• pp.158-167
• /
• 2007

본 논문의 목적은 노외 중성자 선량 감시자를 이용하여 원자로 압력용기 중성자 조사취화의 핵심 요인이 되는 고속중성자 ($1{\ge}MeV$) 조사량 평가 방법을 제시하고 적용성을 검증하는 것이다. 다양한 중성자 반응에너지를 갖는 다수의 선량감시자를 원자로 외벽 보온 단열재와 1차 생물학적 차폐체 사이의 공간에 설치하고 한 주기 동안 조사시킨 후 인출하여 생성핵종에 대한 방사선을 측정하여 반응률을 도출하였다. 또한 상업용 코드를 이용한 중성자 수송계산을 통해 감시자 위치에서의 중성자 스펙트럼을 계산하였다. 두 결과로부터 감시자에 대한 반응률을 직접 비교할 수 있었으며 또한 최소자승 조정 절차를 통해 최적의 중성자 스펙트럼도 도출할 수 있었다. 감시자 측정 결과와 해석적으로 계산한 중성자 조사량 사이에는 관련 규정에서 제시한 ${\pm}30%$ 이내의 오차를 보였다.

• Nuclear Engineering and Technology
• /
• 제7권3호
• /
• pp.191-198
• /
• 1975

혼합 방사선장에서 LiF 열형광 선량계에 의한 중성자 선량측정법에 고나해 연구하였다. 혼합 방사선장에서 중성자선량을 선택적으로 측정하고 평가하기 위해서 $^{6}$LiF 와 $^{7}$LiF 선량계를 속중성자 선량과 열중성자 선량측정에 이용하였다. 개인 방사선 피폭 선량측정에 사용키 위한 보정상수를 유도하였고 중성자와 감마선 선량측정을 위한 그로우곡선을 분석하였다.

• 대한방사선치료학회지
• /
• 제9권1호
• /
• pp.71-81
• /
• 1997

I. Objective and Importance of the Project We have been using MC-50 cyclotron and NT-50 neutron therapy machine for treating cancer patients since 1986 at Korea Cancer Center Hospital. It is mandatory to measure accurately the dose distribution and the total absorbed dose of fast neutron for putting it to the clinical use. At present the methods of measurement of fast neutron are proposed largely by American Associations of Physicists in Medicine (Task Group 18), European Clinical Neutron Dosimetry Group, and International Commission on Radiation Units and Measurements. The complexity of measurement, however, induce the methodological differences between them. In our study, therefore, we tried to establish a unique technique of measurement by means of measuring the emitted doses and the dose distribution of fast neutron beam from neutron therapy machine, and to invent a standard method of measurement adequate to our situation. II. Scope and Contents of the Project For establishing a unique technique of measurement and inventing a standard method of measurement of fast neutron beam, 1. to grasp the physical characteristics of neutron therapy machine 2. to study the principles for measrement of fast neutron beam 3. to get the dose distribution (dose rate, percent-depth dose, flatness etc) throught the actual measurement 4. to compare our data with those being cited world-widely.

• Nuclear Engineering and Technology
• /
• 제55권2호
• /
• pp.756-768
• /
• 2023

Neutron transport calculations are extremely challenging due to the high computational cost of large and complex problems. A multilevel octree grid algorithm (MLTG) of discrete ordinates method was developed to improve the modeling accuracy and simulation efficiency on 3-D Cartesian grids. The Balakovo-3 VVER-1000 neutron dosimetry benchmark is calculated to verify and validate this numerical technique. A simplified S₂ synthetic acceleration is used in the MLTG calculation method to improve the convergence of the source iterations. For the triangularly arranged fuel pins, we adopt a source projection algorithm to generate pin-by-pin source distributions of hexagonal assemblies. MLTG provides accurate geometric modeling and flexible fixed source description at a lower cost than traditional Cartesian grids. The total number of meshes is reduced to 1.9 million from the initial 9.5 million for the Balakovo-3 model. The numerical comparisons show that the MLTG results are in satisfactory agreement with the conventional S_N method and experimental data, within the root-mean-square errors of about 4% and 10%, respectively. Compared to uniform fine meshing, approximately 70% of the computational cost can be saved using the MLTG algorithm for the Balakovo-3 computational model.

• 한국압력기기공학회 논문집
• /
• 제10권1호
• /
• pp.107-112
• /
• 2014

The Code of Federal Regulations, Title 10, Part 50, Appendix H requires surveillance program for reactor pressure vessel(RPV) that the peak neutron fluence at the end of the design life of the vessel will exceed $1.0E+17n/cm^2$ (E>1.0MeV). 2D/1D Synthesis method based on DORT 3.1 transport calculation code has been widely used to determine fast neutron(E>1.0MeV) fluence exposure to RPV in the beltline region. RAPTOR-M3G(RApid Parallel Transport Of Radiation-Multiple 3D Geometries) performing full 3D transport calculation was developed by Westinghouse and KRIST(Korea Reactor Integrity Surveillance Technology) and applied for the evaluations of In-Vessel and Ex-Vessel neutron dosimetry. The reaction rates from measurement and calculation were compared and the results show good agreements each other.

• Journal of Radiation Protection and Research
• /
• 제13권1호
• /
• pp.1-7
• /
• 1988

중성자선량측정을 위하여 방사선과의 상호작용으로 인한 과열된 액체의 기화를 원리로 하는 bubble-damage polymer detector를 개발하였다. acrylamide와 글리세린으로 만든 중합체에 과열상태의 Freon12 액체방울을 분산시켜 검출기를 제작하였으며 중성자 조사에 의해 형성된 기포는 즉각적인 육안 관측이 가능하였다. 검출기의 중성자감도는 Am-Be중성자에 대해 $4{\sim}7bubbles/10{\mu}Sv$이었다.

• 대한방사선방어학회:학술대회논문집
• /
• 대한방사선방어학회 2011년도 추계 학술발표회 및 심포지엄
• /
• pp.290-291
• /
• 2011

• Journal of Radiation Protection and Research
• /
• 제14권2호
• /
• pp.51-62
• /
• 1989

The high efficiency moderated-type neutron spectrometer and doseequivalent counter were developed for the measurement of low level environmental neutrons. By using these detectors, the neutron energy spectra and dose equivalent rates due to skyshine effect were measured in the environment surrounding the accelerator facilities and also the altitude variation of cosmic ray neutrons in the aircraft flying over Japan.