• 제목/요약/키워드: Neutron Irradiation Facility

검색결과 30건 처리시간 0.074초

Measurements of In-phantom Neutron Flux Distribution at the HANARO BNCT Facility

  • Kim Myong Seop;Park Sang Jun;Jun Byung Jin
    • Nuclear Engineering and Technology
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    • 제36권3호
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    • pp.203-209
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    • 2004
  • In-phantom neutron flux distribution is measured at the HANARO BNCT irradiation facility. The measurements are performed with Au foil and wires. The thermal neutron flux and Cd ratio obtained at the HANARO BNCT facility are $1.19{\times}10^9\;n/cm^{2}s$ and 152, respectively, at 24 MW reactor power. The measured in-phantom neutron flux has a maximum value at a depth of 3 mm in the phantom and then decreases rapidly. The maximum flux is about $25\%$ larger than that of the phantom surface, and the measured value at a depth of 22 mm in the phantom is about a half of the maximum value. In addition, the neutron beam is limited well within the aperture of the neutron collimator. The two-dimensional in-phantom neutron flux distribution is determined. Significant neutron irradiation is observed within 20 mm from the phantom surface. The measured neutron flux distribution can be utilized in irradiation planning for a patient.

CHARACTERISTICS OF A NEW PNEUMATIC TRANSFER SYSTEM FOR A NEUTRON ACTIVATION ANALYSIS AT THE HANARO RESEARCH REACTOR

  • Chung, Yong-Sam;Kim, Sun-Ha;Moon, Jong-Hwa;Baek, Sung-Yeol;Kim, Hark-Rho;Kim, Young-Jin
    • Nuclear Engineering and Technology
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    • 제41권6호
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    • pp.813-820
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    • 2009
  • A rapid pneumatic transfer system (PTS) for an instrumental neutron activation analysis (INAA) is developed as an automatic irradiation facility involving the measurement of a short half-life nuclide and a delayed neutron counting system. Three new PTS designs with improved functions were constructed at the HANARO research reactor in 2006. The new system is composed of a manual system and an automatic system for both an INAA and a delayed neutron activation analysis (DNAA). The design and basic conception of a modified PTS are described, and the functions of system operation and control, radiation protection and emissions of radioactive gas are improved. In addition, a form of capsule transportation of these systems is tested. The experimental results pertaining to the irradiation characteristics with variation of the neutron flux and the temperature of the irradiation position with the irradiation time are presented, as is an analysis of the reference material for analytical quality control and uncertainty assessments.

중성자 조사후 Black mouse의 고환 조직 및 정자수 변화에 관한 연구 (Study on Changes of Sperm Count and Testis Tissue in Black Mouse after Neutron Irradiation)

  • 천기정;서원숙;손화영
    • Journal of Radiation Protection and Research
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    • 제31권1호
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    • pp.31-35
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    • 2006
  • Black mouse에 하나로 원자로의 BNCT시설을 이용하여 중성자(flux:1.036739E+09)를 머리를 정면으로 16 및 32 Gy 조사한 후 생물학적 효과를 관찰하는 일환으로 고환에 대한 물리학적 변화 및 조직 변화를 관찰하였다. 조사 후 90일이 경과한 후에 고환의 무게는 변화가 없었으나 고환의 부피는 약간 감소하였으며, 정자수도 감소하였다. 고환의 조직검사에서는 32 Gy 중성자 조사군에서 위축된 정세관의 수가 증가되었으며 stage VI에서의 정세관에서는 정조세포 및 비사기 정모세포가 고갈되어 있음을 알 수 있었다. 중성자 조사(32 Gy)후 고환의 손상이 장기간 경과 후에도 회복되지 않음을 알 수 있었다.

방사성 중성자선원에 의한 방사선방어측정기의 교정을 위한 표준 중성자 조사장치 연구 (Standard Neutron Irradiation Facility for Calibration of Radiation Protection Instruments by Radioactive Neutron Sources)

  • 최길웅;이경주;황선태
    • Journal of Radiation Protection and Research
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    • 제14권1호
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    • pp.66-70
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    • 1989
  • 방사성 중성자선원은 일상적 시험에 있어 표준 중성자 방사선장을 형성하는데 적합하다. 방사선 방어상의 목적으로 사용되는 중성자 측정기기의 교정을 위한 기준 방사선이 ISO TC-85에서 제의되었다. 한국표준연구소 방사선연구실에는 ISO TC-85의 추천사항에 준하여 개인용 중성자 선량계를 교정하기 위하여 $^{252}Cf$$^{241}Am-Be$ 선원을 이용한 표준조사시설을 설립하였다. 본 연구에서는 중성자 산란과 선원 비등방성에 연관된 교정상의 보정인자들을 실험에 의하여 결정하였다.

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The Characteristics for BNCT facility in Hanaro Reactor

  • Soheigh Suh;Lee, Dong-Han;Ji, Young-Hoon;Lee, Dong-Hoon;Yoo, Seong-Yul;Rhee, Chang-Hun;Rhee, Soo-Yong;Jun, Byung-Jin
    • 한국의학물리학회:학술대회논문집
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    • 한국의학물리학회 2002년도 Proceedings
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    • pp.161-163
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    • 2002
  • The BNCT(Boron Neutron Capture Therapy) facility has been developed in Hanaro(High-flux Advanced Neutron Application Reactor), a research reactor of Korea Atomic Energy Research Institute. A typical tangenial beam port is utilized with this BNCT facility. Thermal neutrons can be penetrated within the limits of the possible maximum instead of being filtered fast neutrons and gamma rays as much as possible using the silicon and bismuth single crystals. In addition to, the liquid nitrogen (LN$_2$) is used to cool down the silicon and bismuth single crystals for the increase of the penetrated thermal neutron flux. Neutron beams for BNCT are shielded using the water shutter. The water shutter was designed and manufactured not to interfere with any other subsystem of Hanaro when the BNCT facility is operated. Also, it is replaced with conventional beam port plug in order to cut off helium gas leakage in the beam port. A circular collimator, composed of $\^$6/Li$_2$CO$_3$ and polyethylene compounds, is installed at the irradiation position. The measured neutron flux with 24 MW reactor power using the Au-198 activation analysis method is 8.3${\times}$10$\^$8/ n/cm$^2$ s at the collimator, exit point of neutron beams. Flatness of neutron beams is proven to ${\pm}$ 6.8% at 97 mm collimator. According to the result of acceptance tests of the water shutter, the filling time of water is about 190 seconds and drainage time of it is about 270 seconds. The radiation leakages in the irradiation room are analyzed to near the background level for neutron and 12 mSv/hr in the maximum for gamma by using BF$_3$ proportional counter and GM counter respectively. Therefore, it is verified that the neutron beams from BNCT facility in Hanaro will be enough to utilize for the purpose of clinical and pre-clinical experiment.

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Mechanical performance of additively manufactured austenitic 316L stainless steel

  • Kim, Kyu-Tae
    • Nuclear Engineering and Technology
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    • 제54권1호
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    • pp.244-254
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    • 2022
  • For tensile tests, Vickers hardness tests and microstructure tests, plate-type and box-type specimens of austenitic 316L stainless steels were produced by a conventional machining (CM) process as well as two additive manufacturing processes such as direct metal laser sintering (DMLS) and direct metal tooling (DMT). The specimens were irradiated up to a fast neutron fluence of 3.3 × 109 n/cm2 at a neutron irradiation facility. Mechanical performance of the unirradiated and irradiated specimens were investigated at room temperature and 300 ℃, respectively. The tensile strengths of the DMLS, DMT and CM 316L specimens are in descending order but the elongations are in reverse order, regardless of irradiation and temperature. The ratio of Vickers hardness to ultimate tensile strength was derived to be between 3.21 and 4.01. The additive manufacturing processes exhibit suitable mechanical performance, comparing the tensile strengths and elongations of the conventional machining process.

Chronic Effects of Hair, Blood And Testis In Black Mouse With Neutron Irradiation By Lying Flat Pose

  • Chun, Ki-Jung;Yoo, Bo-Kyung;Kim, Bong-Hee
    • 대한약학회:학술대회논문집
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    • 대한약학회 2003년도 Proceedings of the Convention of the Pharmaceutical Society of Korea Vol.2-2
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    • pp.105.1-105.1
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    • 2003
  • The purpose of this study is to investigate the biological effects in black mouse by neutron irradiation at HANARO reactor in KAERI. Neutrons readily penetrate the charged field of an atomic nucleus because they are electrically neural. And so it can fight cancer with the radiation released when an atom of the element boron absorbs a neutron. The main patient in BNCT facility is brain cancer and sometimes skin cancer in foreign countries until now. Therefore, mice were laid flat and so irradiated at the direction of the front. (omitted)

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