• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.7 no.2
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• pp.73-78
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• 2009

The decay heat of Cs and Sr contained in a LiCl waste salt, generated from an electrolytic reduction process in pyroprocessing of spent nuclear fuel, has been calculated. The calculation has been carried out under some assumptions that most of the LiCl waste is purified and recycled to main process, and the residual is fabricated to make a waste form. As a result, the decay heat from daughter nuclides such as Ba and Y seems to be maximum 4.6 times higher than that from their parent nuclides such as Cs and Sr. The thermal release from Cs and Sr in the LiCl waste is the maximum around the first one month, so an cooling system operation for some time at the beginning would be suggested to control a rapid increase in the temperature of the LiCl waste salt.

• Journal of Soil and Groundwater Environment
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• v.8 no.1
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• pp.9-16
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• 2003

A new method has been proposed and developed that solves the problem of decreasing electroosmotic flow rate by excess $H^{+}$ and precipitation of heavy metal by $OH^{-}$. An electrolytic solution was circulated between the anode and cathode compartments that enabled the pH at the anode and cathode to be controlled. The change of the soil pH by circulation systems affects the operation time, by lowering the rate of increase of the electric potential gradient, and the removal efficiency of heavy metals, by affecting the soil pH. Since there was no effluent from the cathode compartment in circulation system, there was no need to treat the wastewater after the experiment, which resulted in the reduction of influent electrolyte volume.

• Korean Journal of Metals and Materials
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• v.46 no.9
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• pp.577-584
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• 2008

The electrolytic reduction of spent oxide fuel involves the liberation of oxygen in a molten LiCl electrolyte, which results in a chemically aggressive environment that is too corrosive for typical structural materials. So, it is essential to choose the optimum material for the process equipment handling molten salt. In this study, corrosion behavior of Inconel 713LC, Inconel MA 754, Nimonic 80A and Nimonic 90 in the molten salt $LiCl-Li_2O$ under an oxidizing atmosphere was investigated at $650^{\circ}C$ for 72~216 hrs. Inconel 713LC alloy showed the highest corrosion resistance among the examined alloys. Corrosion products of Inconel 713LC were $Cr_2O_3$, $NiCr_2O_4$ and NiO, and those of Inconel MA 754 were $Cr_2O_3$ and $Li_2Ni_8O_{10}$ while $Cr_2O_3$, $LiFeO_2$, $(Cr,Ti)_2O_3$ and $Li_2Ni_8O_{10}$ were produced from Nimonic 80A. Also, corrosion products of Nimonic 90 were found to be $Cr_2O_3$, $(Cr,Ti)_2O_3$, $LiAlO_2$ and $CoCr_2O_4$. Inconel 713LC showed local corrosion behavior and Inconel MA 754, Nimonic 80A, Nimonic 90 showed uniform corrosion behavior.

• Transactions of the Korean hydrogen and new energy society
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• v.34 no.5
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• pp.421-430
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• 2023

Fe-Ni-Pt nanocatalysts were loaded on carbon black powders which were synthesized by a spontaneous reduction reaction of iron (II) acetylacetonate, nickel (II) acetylacetonate and platinum (II) acetylacetonate. The morphology and the loading weight of Fe-Ni-Pt nanoparticles were characterized by transmission electron microscopy and thermogravimetric analyzer. The amount of Fe-Ni-Pt catalyst supported on the carbon black surface was about 6.42-9.28 wt%, and the higher the Fe content and the lower the Pt content, the higher the total amount of the metal catalyst supported. The Brunauer-Emmett-Teller Analysis (BET) specific surface area of carbon black itself without metal nanoparticles supported was 233.9 m²/g, and when metal nanoparticles were introduced, the specific surface area value was greatly reduced. This is because the metal nanocatalyst particles block the pore entrance of the carbon black, and thereby the catalytic activity of the metal catalysts generated inside the pores is reduced. From the I-V curves, as the content of the Pt nanocatalyst increased, the electrolytic properties of water increased, and the activity of the metal nanocatalyst was in the order of Pt > Ni > Fe.

• Korean Chemical Engineering Research
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• v.51 no.6
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• pp.700-708
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• 2013

Pyroprocessing has been developed for the purpose of resolving the current spent nuclear fuel management issue and enhancing the recycle of valuable resources. Pyroprocessing has been developed with the dry technologies which are performed under high temperature conditions excluding any aqueous processes. Pyro-processes which are based on the electrochemical principles require pretreatment processes and a voloxidation process is considered as a pretreatment step for an electrolytic reduction process. Various kinds of gas conditions are applicable to the voloxidation process and the understanding of Cs behavior during the process is of importance for the analyses of waste characteristics and heat load on the overall pyroprocessing. In this study, the changes of chemical compounds with the gas conditions were calculated by analyzing gas-solid reaction behavior based on the chemical equilibria on a Cs-Te-O system. $Cs_2TeO_3$ and $Cs_2TeO_4$ were selected after a Tpp diagram analysis and it was confirmed that they are relatively stable under oxidizing atmospheres while it was shown that Cs and Te would be removed by volatilization under reducing atmosphere at a high temperature. This work provided basic data for predicting Cs behavior during the voloxidation process at which compounds are chemically distributed as the first stage in the pyroprocessing and it is expected that the results would be used for setting up material balances and related purposes.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.5 no.4
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• pp.309-322
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• 2007

This study deals with the irradiation effects on some selected components which are being used in an Advanced Spent Fuel Conditioning Process (ACP). Irradiation test components have a higher priority from the aspect of their reliability because their degradation or failure is able to critically affect the performance of an ACP equipment. Components that we chose for the irradiation tests were the AC servo motor, potentiometer, thermocouples, accelerometer and CCD camera. ACP facility has a number of AC servo motors to move the joints of a manipulator and to operate process equipment. Potentiometers are used for a measurement of several joint angles in a manipulator. Thermocouples are used for a temperature measurement in an electrolytic reduction reactor, a vol-oxidation reactor and a molten salt transfer line. An accelerometer is installed in a slitting machine to forecast an incipient failure during a slitting process. A small CCD camera is used for an in-situ vision monitoring between ACP campaigns. We made use of a gamma-irradiation facility with cobalt-60 source for an irradiation test on the above components because gamma rays from among various radioactive rays are the most significant for electric, electronic and robotic components. Irradiation tests were carried out for enough long time for total doses to be over expected threshold values. Other components except the CCD camera showed a very high radiation hardening characteristic. Characteristic changes at different total doses were investigated and threshold values to warrant at least their performance without a deterioration were evaluated as a result of the irradiation tests.

• The Korean Journal of Physiology
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• v.5 no.2
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• pp.55-62
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• 1971

In an attempt to better understand the effects of whole body X-irradiation on the levels of non-protein sulfhydryl (NP-SH), non-protein disulfide (NP-SS) and oxygen consumption rate $(QO_2)$ of the mouse duodenum, and to clarify the possible radioprotective action of reduced glutathione (GSH), a whole body X-irradiation of 1,000r was given to albino mouse either singularly or immediately after injecting GSH intraperitoneally to mouse 1 mg per gm of body weight. NP-SH was measured by Ellman's method, NP-SS was measured by the electrolytic reduction method described by Dohan and Woodward, and $(QO_2)$ by the Warburg's standard manometric method. The experiment was performed at 1, 6, 12 and 24 hours post-irradiation, and the comparison was made with the control. The results thus obtained are summarized as follows: 1) Comparing with the intrinsic NP-SH level of $3.31{\pm}0.27{\mu}\;mol/gm$ wet weight in the duodenum of the normal mouse, either whale body X-irradiation or injection of GSH alone produced no significant change in NP-SH from the normal. However, when GSH was injected prior to X-irradiation, markedly elevated NP-SH levels were observed throughout the entire experiment with the highest value of $4.70{\pm}0.10$ at 6 experimental hours. 2) The normal value of NP-SS in the mouse duodenum was $1.57{\pm}0.17{\mu}\;mol/gm$ wet weight, while in the group where injection of GSH and X-irradiation were combined, NP-SS increased to $2.36{\pm}0.33$ at 12 hours and $2.15{\pm}0.53$ at 24 hours, showing the intermediate value between the GSH injection group and X·irradiation group. 3) The normal value of $(QO_2)$ was $4.16{\pm}0.73{\mu}l\;O_2/hr./gm$ D.W., and no noticeable change was observed comparing with the GSH injection group. However, in the group where X·irradiation alone was given, $(QO_2)$ of the duodenum increased significantly throughout the entire experiment with the highest value of $6.35{\pm}1.07$ at 6 experimental hours. When GSH was injected before X-irradiation was given, the levels of $(QO_2)$ were in the middle of the GSH injection group and X-irradiation group. 4) The above results suggest that GSH may be effective as a radioprotector in terms of NP-SH, NP-SS and $(QO_2)$ of the mouse duodenum.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.13 no.4
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• pp.263-269
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• 2015

It is necessary to investigate the electrodeposition behavior of uranium and other elements on the cathode in the electrorefining process to recover the uranium selectively from the reduced metals of the electrolytic reduction process since transuranic elements and rare earth elements is dissolved in the LiCl-KCl eutectic salt. Study on separation factors of U, Ce, Y and Nd based on U and Ce was performed to investigate the deposition behavior of the cathode with respect to the concentration of rare earth elements in LiCl-KCl eutectic salt. After electrorefining with constant current mode by using Ce metal as a sacrifice anode, the contents of U, Ce, Y and Nd in the salt phase and the deposit phase of the cathode were analyzed, and separation factors of the elements were obtained from the analyses. Securing conditions of pure uranium recovery in the elctrorefining process was investigated by considering the separation factors with respect to $UCl_3$ and $CeCl_3/UCl_3$ ratio.

• The Korean Journal of Physiology
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• v.6 no.1
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• pp.11-18
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• 1972

In an attempt to observe the Possible radioprotective actions of single or combined application of reduced glutathione (GSH) and cold exposure in mammals, the albino mouse was subjected to GSH injection, cold exposure at $-1{\pm}0.2C$ and whole-body X-irradiation with 900r either singularly or in combination, or the X-irradiation following the cold exposure and/or GSH injection. The levels of intrinsic NP-SH and NP-SS of the liver, brain and heart were measured at one hour after each application, and the results were compared with the control, i.e., non-irradiated and non-cold exposed normal animal. NP-SH was measured by the Ellman's method, and NP-SS was measured by the electrolytic reduction method described by Dohan and Woodward. The results thus obtained are summarized as follows: 1) The levels of NP-SH in the liver, brain and heart of the normal mouse was $6.35{\pm}0.61,\;2.65{\pm}0.15\;and\;3.17{\pm}0.10{\mu}\;mol/gm\;wet\;wt.$, respectively, and NP-SS was $3.09{\pm}0.11,\;2.95{\pm}0.20\;and\;0.18{\pm}0.24{\mu}\;mol/gm\;wet\;wt.$, respectively. 2) Though there were some degrees of difference among the tissues studied, a general tendency of (1) elevated NP-SH and NP-SS levels in the GSH injection group, (2) similar or slightly elevated NP-SH and NP-SS levels in the cold-exposed group, and (3) markedly decreased levels of NP-SH and NP-SS in the X-irradiated group, was observed. When GSH was injected prior to the X-irradiation, NP-SH and NP-SS in all the tissues studied showed generally higher values than in the group where the X-irradiation was given alone, and the values were close to the normal. In the group where the cold exposure was applied immediately after the X-irradiation, no significant difference was observed in the NP-SH and NP-S5 levels comparing with the X-irradiation group. On the contrary, when GSH was injected immediately prior to the X-irradiation or cold exposure, NP-SH and NP-SS levels were either similar to, or higher than, the normal value.

• KSBB Journal
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• v.19 no.2
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• pp.93-97
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• 2004

We investigate the effect of enzyme pretreatment using protease, carbohydrase, and lipase on improvement of sludge treatment efficiency by measuring SCOD and TCOD. The enzyme-pretreatment increases SCOD of excess sludge. In addition, the amount of sludge reduction during digestion, in terms of SCOD and TCOD, are enhanced by enzyme-pretreatment. Among pretense, carbohydrase, and lipase, pretense showed the best enhancement of the sludge treatment efficiency. Sludge digestion followed by ozone and enzyme treatments showed more effective sludge treatment when compared with ozone treatment alone. Therefore, we expect that enzyme pretreatment can be used as a useful tool for enhancing the sludge treatment efficiency.