Zobrazeno 1 - 10
of 22
pro vyhledávání: '"Woo Nyun Choi"'
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 7, Pp 2606-2613 (2022)
Spent resin often exceeds radiation limits for safe disposal, creating a need for commercial-scale treatment techniques to reduce resin radioactivity. In this study, the radiological safety of a commercialized spent resin treatment device with a trea
Externí odkaz:
https://doaj.org/article/5826da58429942e3a886f3c697705d0b
Evaluation of dose received by workers while repairing a failed spent resin mixture treatment device
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 2, Pp 442-448 (2022)
Intermediate-level radioactive waste (ILW) is not subject to legal approval for cave disposal in Korea. To solve this problem, a spent resin treatment device that separates 14C-containing resin from zeolite/activated carbon and desorbs 14C through a
Externí odkaz:
https://doaj.org/article/40dfef17d8fc424c9f96144719237851
Radiological analysis of transport and storage container for very low-level liquid radioactive waste
Autor:
Seung Hun Shin, Woo Nyun Choi, Seungbin Yoon, Un Jang Lee, Hye Min Park, Seong Hee Park, Youn Jun Kim, Hee Reyoung Kim
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 12, Pp 4137-4141 (2021)
As NPPs continue to operate, liquid waste continues to be generated, and containers are needed to store and transport them at low cost and high capacity. To transport and store liquid phase very low-level radioactive waste (VLLW), a container is desi
Externí odkaz:
https://doaj.org/article/76e7278296a14db2878dd8c48faea37c
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 11, Pp 3824-3836 (2021)
Workers’ safety from radiological exposure in a 1 ton/day capacity spent resin treatment facility was evaluated according to the operating times and outflow rate due to process related leakages. The conservative annual dose based on the operating t
Externí odkaz:
https://doaj.org/article/c085d7d0e3974d08a4a49164f6e4afbe
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 1, Pp 273-281 (2021)
The radiological safety of the spent resin treatment facility with a14C treatment capacity of 1 ton/day was evaluated in terms of the external and internal exposure of worker according to operation scenario. In terms of external dose, the annual dose
Externí odkaz:
https://doaj.org/article/6fad2cdc6f2e40a999f355c06c27ac2f
Publikováno v:
Nuclear Engineering and Technology, Vol 51, Iss 7, Pp 1828-1834 (2019)
The performance of a plastic scintillator for use in an in situ measurement system was analyzed using simulation and experimental methods. The experimental results of four major pure beta-emitting radionuclides, namely 3H, 14C, 32P, and 90Sr/90Y, wer
Externí odkaz:
https://doaj.org/article/1db380c4210b4ccfb61109f62bb9e9f0
Publikováno v:
Nuclear Engineering and Technology, Vol 51, Iss 4, Pp 1169-1175 (2019)
The minimum detectable activity (MDA) value was derived according to the flow rate of the sample and degree of amplification of the device by sending the sample directly from the collection site to the detection part through a pump. This method can l
Externí odkaz:
https://doaj.org/article/c5d1986e01d24f90ab6769b57201c110
Publikováno v:
International Journal of Energy Research. 46:10668-10676
Radiological analysis of transport and storage container for very low-level liquid radioactive waste
Autor:
Youn Jun Kim, Un Jang Lee, Seung Hun Shin, Hye Min Park, Woo Nyun Choi, Seungbin Yoon, Seong Hee Park, Hee Reyoung Kim
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 12, Pp 4137-4141 (2021)
As NPPs continue to operate, liquid waste continues to be generated, and containers are needed to store and transport them at low cost and high capacity. To transport and store liquid phase very low-level radioactive waste (VLLW), a container is desi