It is essential to develop the shield for the extraction of high quality neutron beam and safe work at the sample position. The aim of this study is design, fabrication and filling of the shield in domestic. In consideration of ST-3 beam port of HANARO, we designed the reflectometer shield composed of 14 blocks and fabricated it shield casemate. Through the assembly and quality test of the shield casemate, we established the method of fabrication for neutron beam path and channel. In order to increase shield capacity, we filled shield casemate with heavy concrete, lead ingot and polyethylene that mixed B4C powder and epoxy. The average density of the filled heavy concrete was 4.7g/cm3, which can protect neutron and gamma ray effectively. Also, we developed ancillary equipment such as beam gate unit(BGU, vertical type) for the effective opening and closing of neutron beam. Shielding block was proved by suitable thickness as result that measure surface dosage using of detector and TLD. The acquired technique of design, fabrication and filling of ancillary equipment development can be applicable to the development of shield for the other neutron spectrometer in future.

방사선물질의 수송 및 저장용기 등에 사용되는 에폭시수지계 중섣자 차폐재, KNS-201, KNS-301 및 KNS-601을 제조하였다. 기본물질은 개질 및 수소 첨가된 비스페놀 A형 그리고 노블락형 에폭시수지이며, 첨가제로는 수산화알루미늄 및 탄화붕소이다. 이들 중성자 차폐재들의 열적 및 역학적 성질 및 재방사선성 등을 평가하기 위해 여러 특성시험을 행하였다. 조사된 제반 특성들은 열분해온도;257~280˚C, 열전도도;0.95~1.14W/m.K, 열팽창계수 ;0.77~1.26x10-6˚C-1, 연소특성;800˚C이하, 평균연소시간;5초 이하, 평균연소길이 ;5mm 이하, 인장강도;2.5~3.2Kg/mm2,압축강도:13.2~15.2kg/mm2 굴곡강도:5.2~604Kg/mm2 등을 나타냈다. 전반적으로 개발된 중성자 차폐재들의 관련 특성들이 외국에서 사용되는 중성자 차폐재, NS-4-RF보다 우수한 것으로 나타났다. 또한 KNS-601의 내방사선성이 KNS-201과 KNS-301보다 우수한 것으로 나타났다. 또한 KNS-601의 내방사선이 KNS-201과 KNS-301보다 우수한 것으로 나타났다.

This research is to investigate the effect of borosilicate glass powder on neutron shielding capability of cement mortar. The average particle size of the borosilicate glass powder was 13 μm. It was found that the addition of borosilicate glass powder increased 28 day compressive strength. In addition, neutron shielding capability of cement mortar also increased by the addition of borosilicate glass powder. Considering our earlier findings on enhanced thermal neutron shielding of cement mortar by borosilicate glass powder, the use of borosilicate glass powder was found to be effective to shield neutron when the cement mortar was exposed to the neutron radiation. It can be concluded that borosilicate glass powder is a good alternative material for neutron shielding purposes.