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REFERENCE LINKING PLATFORM OF KOREA S&T JOURNALS
> Journal Vol & Issue
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
Journal Basic Information
Journal DOI :
The Korean Radioactive Waste Society
Editor in Chief :
Volume & Issues
Volume 7, Issue 4 - Dec 2009
Volume 7, Issue 3 - Sep 2009
Volume 7, Issue 2 - Jun 2009
Volume 7, Issue 1 - Mar 2009
Selecting the target year
Behavior Characteristic in Reactor Coolant from Korean PWR NPP's
Kang, Duk-Won ; Yang, Yang-Hee ; Park, Kyong-Rok ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 7, issue 1, 2009, Pages 1~7
This study has been focused on determining the chemical composition of
- in terms of both organic and inorganic
contents - in reactor coolant from 3 different PWR's reactor type. The purpose was to evaluate the characteristic of
that can serve as a basis for reliable estimation of the environmental release at domestic PWR sites.
is the most important nuclide in the inventory, since it contributes one of the main dose contributors in future release scenarios. The reason for this is its high mobility in the environment, biological availability and long half-life(5730yr). More recent studies - where a more detailed investigation of organic
species believed to be formed in the coolant under reducing conditions have been made - show that the organic compounds not only are limited to hydrocarbons and CO. Possible organic compounds formed including formaldehyde, formic acid and acetic acid, etc. Under oxidizing conditions shows the oxidized carbon forms, possibly mainly carbon dioxide and bicarbonate forms. Measurements of organic and inorganic
in various water systems were also performed. The
inventory in the reactor water was found to be 3.1 GBq/kg in PWR of which less than 10% was in inorganic form. Generally, the
activity in the water was divided equally between the gas- and water- phase. Even though organic
compound shows that dominant species during the reactor operation, But during the releasing of
from the plant stack, chemical forms of
shows the different composition due to the operation conditions such as temperature, pH, volume control tank venting and shut down chemistry.
A mite Element Modeling for the Puncture Drop Test of a Cask with the Failure of Impact Limiter
Kwon, Kie-Chan ; Seo, Ki-Seog ; You, Gil-Sung ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 7, issue 1, 2009, Pages 9~16
Transport package for radioactive material should be structurally safe under puncture drop condition and its safety should be verified by test and numerical analysis. Most finite element analyses for puncture drop have been performed without modeling the impact limiter since failure is occurred in the materials of the impact limiter. This paper presents a new modeling methodology, where an element is eroded in case that the material's failure criteria are reached at the element's integration point, to investigate the effect of the impact limiter in the puncture process. The effectiveness of the proposed scheme is shown through the puncture drop analysis of hotcell transport cask, which is under design in KAERI. The results show that about 80 percent of the total impact energy is absorbed due to the deformation of impact limiter. Using the present method the puncture drop can be analyzed more accurately, but it would give conservative results compared to the actual test condition.
Determination of Radiolysis Produce of DHOA by GC/MS
Yang, Han-Beom ; Lee, Eil-Hee ; Lim, Jae-Kwan ; Chung, Dong-Yong ; Kim, Kwang-Wook ; Kim, Jong-Seung ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 7, issue 1, 2009, Pages 17~23
Dihexyloctanamide(DHOA) was used as an extractant or phase modifier with the diamide extractants in a solvent extraction process for a radioactive liquid waste treatment. The degradation compounds of the DHOA extractant, irradiated with
gamma ray, were octanoic acid and dihexylamine which are identified by a Fourier transform infrared(FT-IR) and gas chromatograph/mass spectrometer(GC/MS) analysis, and determined by the GC/MS with selected ion monitoring(SIM) mode. Retention behavior of octanoic acid, tridecane (internal standard) and dihexylamine in total ion chromatogram (TIC) were 8.65 min., 9.79 min., and 10.27 min., respectively. With increasing the absorbed dose of the
-ray irradiated DHOA, the concentration of octanoic acid was decreased and that of dihexylamine was increased.
and Its Activity Level in the Korean Soil
Lee, Chang-Woo ; Chung, Kun-Ho ; Cho, Young-Hyun ; Kang, Mun-Ja ; Lee, Wan-No ; Kim, Hee-Reyoung ; Choi, Geun-Sik ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 7, issue 1, 2009, Pages 25~31
An analytical method of
concentration in soil was set up and discussed considering the
concentration in Korean soil measured with its analytical method. A selective TEVA resin was used to separate and purify the
in the soil sample.
from a commercial
generator was used as a yield tracer for the chemical separation of
and its problem when using
as a tracer was discussed. The chemical recovery yield of
was above 70%. The optimum conditions of inductively coupled plasma mass spectrometry system(ICP-MS) were set up to determine the
after the separation process. The minimum detectable activity(MDA) was 15 mBq/kg-dry in this analytical procedure. The
concentration in soils of Jeju and Kori were measured in the rage of 33.73-89.16 mBq/kg-dry. Those values were less than those reported in other countries and seemed to be originated from atmospheric fallout.
Artificial Weathering of Biotite and Uranium Sorption Characteristics
Lee, Seung-Yeop ; Baik, Min-Hoon ; Lee, Jae-Kwang ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 7, issue 1, 2009, Pages 33~38
An experiment for uranium sorption onto fresh and weathered biotites was performed. After centrifugation, concentrations of uranium in the supernatants were analyzed using ICP-MS, and biotite samples were investigated using XRD and SEM. With powdered biotites (<3 mm in size), we have conducted uranium sorption experiments about fresh and weathered biotites to obtain uranium sorption amounts in various pH conditions. The uranium sorption was not high at a low pH (e.g., pH 3), but increased with increasing pH. There were lower uranium sorption by the weathered biotites than by the fresh ones, and the difference was much larger at higher pH (e.g., pH 11). The lower sorption values of uranium by the weathered biotites may be caused by a change of mineral surfaces and a chemical behavior of surrounding dissolved elements. It seems that the uranium-mineral interaction has been diminished, especially, in the weathered biotite by a destruction and dissolution of preferential sorption sites on the mineral surfaces and by the colloidal formation from dissolved elements.
An Intercomparison of Model Predictions for an Urban Contamination Resulting from the Explosion of a Radiological Dispersal Device
Hwang, Won-Tae ; Jeong, Hyo-Jun ; Kim, Eun-Han ; Han, Moon-Hee ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 7, issue 1, 2009, Pages 39~47
The METRO-K is a model for a radiological dose assessment due to a radioactive contamination in the Korean urban environment. The model has been taken part in the Urban Remediation Working Group within the IAEA's (International Atomic Energy Agency) EMRAS (
) program. The Working Croup designed for the intercomparison of radioactive contamination to be resulted from the explosion of a radiological dispersal device in a hypothetical city. This paper dealt intensively with a part among a lot of predictive results which had been performed in the EMRAS program. The predictive results of three different models (METRO-K, RESRAD-RDD, CPHR) were submitted to the Working Group. The gap of predictive results was due to the difference of mathemathical modeling approaches, parameter values, understanding of assessors. Even if final results (for example, dose rates from contamintaed surfaces which might affect to a receptor) are similar, the understanding on the contribution of contaminated surfaces showed a great difference. Judging from the authors, it is due to the lack of understanding and information on radioactive terrors as well as the social and cultural gaps which assessors have been experienced. Therefore, it can be known that the experience of assessors and their subjective judgements might be important factors to get reliable results. If the acquisition of a little additional information is possible, it was identified that the METRO-K might be a useful tool for decision support against contamination resulting from radioactive terrors by improving the existing model.
The Public Sphere and the Conflict-Structure in Spent Nuclear Fuel Management
Choi, Seong-Kyung ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 7, issue 1, 2009, Pages 49~62
Social Acceptance is important to decide policy of spent nuclear fuel management. The idea of a public sphere as a receptacle of dynamic process is the core in this discussion. The purpose of this study is to examine the concept, participants, the conflict-structure and agreeable conditions of a public sphere. A public sphere means in this paper, mechanism and systems that various stakeholders' and public's participation with spontaneous will can affect decision-making process. For good designing and implementing a public sphere, it is necessary to analysis and cope with political, foreign and security, economic, sociocultural environments, the law and systems around spent nuclear fuel management.
Roles and Importance of Microbes in the Radioactive Waste Disposal
Baik, Min-Hoon ; Lee, Seung-Yeop ; Roh, Yeol ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 7, issue 1, 2009, Pages 63~72
Recently the importance and interest for the microbes has been increased because several important results for the effects of microbes on the radioactive waste disposal have been published continuously. In this study, research status and major results on the various roles and effects of microbes in the radioactive waste disposal have been investigated. We investigated and summarized the roles and major results of microbes in a multi-barrier system consisting of an engineered barrier and a natural barrier which is considered in radioactive waste disposal systems. For the engineered barrier, we discussed about the effects of microbes on the corrosion of a waste container and investigated the survival possibility and roles of microbes in a compacted bentonite buffer. For the natural barrier, the roles of microbes present in groundwaters and rocks were discussed and summarized with major results from natural analogue studies. Furthermore, we investigated and summarized the roles and various interactions processes of microbes and their effects on the radionuclide migration and retardation including recent research status. Therefore, it is expected that the effects and roles of microbes on the radioactive waste disposal can be rigorously evaluated if further researches are carried out for a long-term behavior of the disposal system in the deep geological environments and for the effects of microbes on the radionuclide migration through geological media.