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고체비적검출기(固體飛跡檢出器)를 이용(利用)한 중성자선량(中性子線量) 측정(測定)
육종철,노성기,Yook, Chong-Chul,Ro, Seung-Gy 대한방사선방어학회 1977 방사선방어학회지 Vol.2 No.1
중성자(中性子) 선량(線量) 측정목적(測定目的)으로 사용(使用)할 Posi필름 고체비적검출기(固體飛跡檢出器)의 알파입자(粒子) 비적검출(飛跡檢出) 효율(效率)과 화학부식(化學腐蝕)에 의(依)한 그의 비적형성(飛跡形成) 최적조건(最適條件)을 실험적(實驗的)으로 결정(決定)하였다. $^{10}B$ 및 $^{27}Al$박(箔)과 posi 필름 고체비적검출기(固體飛跡檢出器)로 이루어진 중성자(中性子) 선량계(線量計)를 제작(製作)하고 이것에 의(依)한 중성자(中性子) 선속밀도(線束密度) 및 선량(線量)의 측정범위등(測定範圍等)을 실험결과(實驗結果)와 이론적(理論的)인 근거하(根據下)에서 산출(算出)하였다. 그 결과(結果) posi 필름 고체비적검출기(固體飛跡檢出器)는 핵분열성(核分裂性) 물질(物質)을 입자방출체(粒子放出體)로 병용(倂用)함이 없이 중성자(中性子) 측정(測定)에 효과적(效果的)으로 응용(應用)될 수 있음이 판명(判明)되었다. A base of photographic posi-film which is commecially available has been found to be a possible alpha-particle track detector. Its neutron dosimetric characteristics, i. e., alpha-particle track registrating efficiency and optimum condition of track formation by chemical etching, have been determined experimentally. The range of neutron fluence and dose capable of being measured by a neutron dosimeter consisting of alpha-particle radiator foils $(^{10}B\;and\;^{27}Al)$ and posi-flim solid state track detector, has been estimated on the basis of experimental results and theoryetical background. This detector seems to be useful for neutron dosimetry because of many favorable properties, i. e., simplicity, cheapness and a wide range of sensitivitiy.
육종철,고병준,박용집 대한전기학회 1970 전기의 세계 Vol.19 No.4
A neutron detector, in general, can not be utilized as the thermal neutron detecting chamber in the nuclear power reactor, especially P.W.R. due to the characteristics of high temperature, high pressure and high neutron flux in a reactor vessel. We have performed an experiment to detect the thermal neutrons at 400.deg. C and high flux of thermal neutron in a power reactor. Coating boron-10 on the aluminium plates by means of surface diffusion method at 600.deg. C for 5 hours in an electric furace, also we made a typical chamber which was compensated ionization chamber filled with free air as an ionization gas. It was checked the chamber characteristics in the TRIGA MARK-II Reactor at the power level from zero to 250KW. The chamber current showed a perfect linear increase to power increase. However, many variation of the measured current were observed within the power of 50KW.