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[en] The Korean government promulgated the 4th Comprehensive Nuclear Energy Promotion Plan (CNEPP) in November 2011, which included the objectives and strategies with the overriding priority that the Korean government and nuclear institutes should carry forward to achieve over next 5 years. Since 1997, when the first CNEPP was promulgated, the Korean government has modified and supplemented the CNEPP every 5 years based on an analysis of the outcomes of the previous CNEPP as well as the outlook on the future nuclear energy uses and developments in domestic and foreign countries. This paper reviews the history of the CNEPP and gives a general idea of the 4th CNEPP. (orig.)
[en] Since nuclear terrorism has been identified as a real threat, the Korean government has earnestly developed elementary technologies and sub-systems for establishing an integrated defensive system against nuclear terrorism, which is based on the concept of defense-in-depth. This paper introduces the gist and implications of the studies that have been conducted in building the national nuclear material tracking system for preventing and intercepting the illicit trafficking and transporting of nuclear material in Korea. (orig.)
[en] Recently, there have been grave concerns that the anticipated increase in the use of nuclear energy worldwide could result in dissemination of sensitive nuclear technologies. To meet the increase in nuclear energy demand and strengthen the non-proliferation regime simultaneously, the various proposals for 'multilateralization of nuclear fuel cycle' have been widely suggested. Those proposals are expected to have serious impacts on our country, if they has come true. In this paper, therefore, the 12 existing proposals were reviewed and assessed for their potential impacts on our country, in order to help prepare the appropriate measures responding to the international attempt of 'multilateralization of nuclear fuel cycle'
[en] The smooth construction and operation of nuclear facilities requires understanding and support of both the local residents and the national people. It is essential that our country, which should maintain using nuclear energy for national energy security and economic growth, shall improve the social acceptance of nuclear energy. In order to identify the level of social acceptance of nuclear energy, this study investigated the perception of the local residents in Gyeongju and the public in other areas on a nuclear power plant and a low- and intermediate-level radioactive waste disposal facility through an individual interview. The subjects of the investigation were 450 persons. This study identified that perceptions of the respondents were somewhat dependent on the residential area, and derived the implications to be reflected in establishing the customized public-relation strategies.
[en] This study examines how much the radiation dose rate around it varies if a crack occurs on the spent nuclear fuel rod. The spent nuclear fuel rod to be examined is that of Kori unit 3 and 4. The source terms are evaluated using the ORIGEN-ARP that is part of the version 5.1 of the SCALE package. The radiation dose rate is assessed using the TORT. To check if the structure of a fuel rod is appropriately modeled in the TORT calculation, the calculation results by the TORT are compared with those by the ANISN for the same case. From the code simulation, it is known that if a crack occurs on the spent nuclear fuel rod, the neutron dose rate varies depending on what material is the crack filled with, but the gamma dose rate varies irrespective of type of the material that the crack is filled with
[en] As of August 2020, there are 30 nuclear power reactors in the Republic of Korea as shown in Table 1 and Figure 1. Among those reactors, 24 nuclear power reactors are in operation; four reactors (Shin Hanul units 1 and 2 and Shin Kori units 5 and 6) are under construction, and two reactors (Kori unit 1 and Wolsong unit 1) are permanently shut down.
[en] Spent nuclear fuel should be kept under safe and strict management until they can be disposed of permanently. For this, it is important to understand the radiation release characteristics from the spent nuclear fuel. In this paper, hence, Monte Carlo method is applied to evaluate 2 types of PWR spent fuel assembly generated from the operating plants in Korea: Westinghouse- and KSNP-type. The source terms were calculated using ORIGEN-ARP. The neutron and photon (or gamma) dose distributions along the vertical and horizontal directions of the fuel assembly were evaluated using MCNPX code. Compared with the 2 dose distributions, the photon dose was found to be about 105 times higher than the neutron dose. (orig.)
[en] A fiber-optic radiation sensor (FORS) was developed to measure the gamma radiation from radioactive contaminated soil. The FORS was fabricated using an inorganic scintillator (Lu,Y)2SiO5:Ce (LYSO:Ce), a mixture of epoxy resin and hardener, aluminum foil, and a plastic optical fiber. Before its real application, the FORS was tested to determine if it performed adequately. The test result showed that the measurements by the FORS adequately followed the theoretically estimated values. Then, the FORS was applied to measure the gamma radiation from radioactive contaminated soil. For comparison, a commercial radiation detector was also applied to measure the same soil samples. The measurement data were analyzed by using a statistical parameter, the critical level to determine if net radioactivity statistically different from background was present in the soil sample. The analysis showed that the soil sample had radioactivity distinguishable from background.
[en] A fiber-optic temperature sensor (FOTS) using an infrared optical fiber was developed and applied to remote and real-time measurements of the temperature of the water in a spent nuclear fuel pool (SNFP) at a nuclear power plant (NPP). In this study, metal caps were employed as the sensing probe of the FOTS owing to their high thermal conductivity. An infrared optical fiber, PIR AgCl:AgBr polycrystalline fiber, was used to transmit the infrared light emitted from the water at a certain temperature. The FOTS was used to measure the temperature of the water in oil bath by changing the temperature in 5 ◦C increments over the range from 30 to 70 ◦C. The temperatures measured by using the FOTS with a metal cap varied almost linearly over that range, which means that the FOTS with a metal cap can be used as an auxiliary monitoring system for measuring the temperature of the water in a SNFP water temperature.
[en] In this research, we developed and characterized a phoswich radiation sensor (PHORS) to simultaneously measure the count rates and the energies of beta and gamma radiation. The proposed PHORS device comprises a sensing probe combining NaI(Tl) and CaF2(Eu) scintillators for simultaneous measurement of beta and gamma radiation, a multichannel analyzer to characterize the radiation energy, and a laptop computer for signal analysis. For its performance test, we employed a prototype PHORS to measure the energies and the count rates of beta and gamma radiation from three different radiation sources for separation distances from 2 to 10 cm. The count rates of the PHORS were consistent with expected rates, and the captured energy spectra showed classic radionuclide characteristics. Thus, the proposed PHORS system provides an effective and facile tool to detect beta and gamma radiation simultaneously and to identify radionuclides from the captured energy spectra.