• Proceedings of the Korean Institute of Building Construction Conference
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• 2017.11a
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• pp.155-156
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• 2017

Borosilicate glass was incorporated to improve the neutron shielding capability of concrete. Boron is a typical neutron shielding material, and it is contained in borosilicate glass. However, borosilicate glass causes alkali-silica reaction, which damages the concrete. Therefore, studied to reduce the expansion due to alkali-silica reaction and to improve the neuton shielding capability. The measurement of the expansion due to the alkali-silica reaction was based on ASTM C 1260. Experimental results show that the expansion due to alkali-silica reaction is reduced when borosilicate glass powder incorporated. In addition, the neutron shielding capability was significantly improved when the fine aggregate replaced with borosilicate glass.

• Nuclear Engineering and Technology
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• v.3 no.4
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• pp.185-197
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• 1971

Korea's TRIGA Mark-Ⅱ reactor was primarily designed in 1950's and was constructed in 1962 for 100 kw thermal output, but it was upgraded to 250 kw in July 1969. Nevertheless, the shield remains unchanged, although the radiation level has increased. The result of computation On this paper shows that, with the existing shield, it is safe for the fast neutrons even after the power upgrading by 2.5 times. It is, however, somewhat dangerous for the gamma rays which are comprised of primary and secondary. For the analysis of the reactor shielding design, an attempt is made for the computation toward the horizontal direction. From theoretical point of view, it can be concluded that some layer of additional shield must be reinforced to the existing concrete in order to be radiologically safe in the reactor hall.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.10a
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• pp.318-318
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• 1998

• Proceedings of the Korean Nuclear Society Conference
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• 2002.05a
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• pp.222.1-222
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• 2002

• Proceedings of the Korean Nuclear Society Conference
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• 2002.05a
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• pp.436.2-436
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• 2002

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2011.10a
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• pp.65-66
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• 2011

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05a
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• pp.163-168
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• 1998

경수로 압력용기의 취화는 주로 고속 중성자에 기인한다. 경수로 압력용기를 모의한 PCA-REPLICA실험을 해석하여 원자력 시설의 구조재로 쓰이는 철의 핵자료 검증과 MATXS/TRANSX/DANTSYS 계산체제의 유용성을 확인하고자 하였다. 라이브러리는 JEF-2.2를 이용한 KAFAX-F22가 기본 자료로 이용되었고, 이밖에 ENDF/B-Vl.1과 JENDI.-3.2의 철 핵자료도 비교 검증하였다. 계산결과는 실험오차 등을 고려하면 측정치와 근접하는 경향을 보였고, 앞으로 개발될 차폐해석용 라이브러리 검증에 유용한 자료가 될 수 있겠다.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.10a
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• pp.103-108
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• 1997

압력용기로의 속중성자 조사량 평가를 4군 노달 노심해석코드로 수행하였다. 이 코드는 MCNP에 비해 정확성은 떨어지나, 핵연료 연소의 효과나 핵연료 장전 모형의 영향을 쉽게 고려할 수 있었다. 속중성자 조사량 감소 방안으로서 반사체 차폐 구조물을 설치하는 방안과 노심외곽에 대체 핵연료 집합체를 장전하는 방안을 비교하였다. 신형원전의 경우 가장 효과적인 방안은 물 반사체 영역에 금속 차폐 구조물을 설치하는 것이나 운전중인 원자로의 경우 비록 주기길이의 감소와 핵연료 비용의 증가는 있으나 속중성자 감소 효과에 있어서는 대체 핵연료 집합체의 장전이 대안일 수 있다.

• Journal of Radiation Protection and Research
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• v.32 no.4
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• pp.158-167
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• 2007

It is required that the neutron dosimetry be present to monitor the reactor vessel throughout its plant life. The Ex-vessel Neutron Dosimetry Systems which consist of sensor sets, radiometric monitors, gradient chains, and support hardware have been installed for 3-Loop plants after a complete withdrawal of all six in-vessel surveillance capsules. The systems have been installed in the reactor cavity annulus in order to characterize the neutron energy spectrum over the beltline region of the reactor vessel. The installed dosimetry were withdrawn and evaluated after a irradiation during one cycle and then compared to the cycle specific neutron transport calculations. The reaction rates from the measurement and calculation were compared and the results show good agreements each other.

• Applied Chemistry for Engineering
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• v.8 no.1
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• pp.92-98
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• 1997

Effects of radiation dose on mechanical properties such as tensile strength, compressive strength, flexural strength, specific gravity and changes of weight and hydrogen content of epoxy resin-type neutron shielding materials to be used for spent fuel shipping casks have been investigated. At radiation dose up to 0.5MGy, the tensile strength, compressive strength and flexural strength of the shielding materials of KNS-115A, KNS-115B and KNS-115C have been increased with increase in the radiation dose. In contract, these mechanical properties have been decreased at radiation dose above 0.5MGy. The amount of radiation dose on the materials of KNS-115A, KNS-115B and KNS-115C has not resulted in a measurable loss of specific gravity and weight of them, whereas the reduction of hydrogen content has been observed.