Abstract: A method of manufacturing metal nanoparticles by mixing a metal precursor with a solvent to prepare a mixed solution, and radiating the mixed solution with an ion beam to reduce the metal precursor and produce the metal nanoparticles. In addition, when metal nanoparticles are prepared by using an ion beam, uniform-sized metal nanoparticles can be mass produced.

Abstract: The present invention relates to a longitudinally divided emergency core cooling (ECC) duct in order to efficiently inject safety water to core of a pressurized light-water nuclear reactor. The ECC duct includes side supports for preventing the flow-induced vibration in the annular downcomer, and has structural stability while thermally expanding and contracting. A longitudinally divided ECC duct for emergency core cooling water injection of a nuclear reactor is provided on the periphery of a core barrel of a nuclear reactor, includes an emergency core cooling water inlet facing a direct vessel injection nozzle, and extends in a longitudinal direction of the core barrel. The longitudinally divided ECC duct is divided into a plurality of longitudinally-divided ducts in the longitudinal direction of the longitudinally divided ECC duct.

Abstract: An apparatus and system for separating remaining powder of hulls includes a first remaining powder separating unit to be supplied with hulls of a spent nuclear fuel subjected to a high-temperature oxidation, and to include a first brush for separating remaining powder of the hulls; a hull alignment unit to be supplied with the hulls from the first remaining powder separating unit, and to align the hulls; a second remaining powder separating unit to be supplied with the aligned hulls from the hull alignment unit, and to include a second brush for separating remaining powder adhered on an inner peripheral surface of the hulls; and a third remaining powder separating unit to be supplied with the hulls from the second remaining powder separating unit, and to separate the remaining powder remaining on the inner/outer peripheral surface of the hulls by using air.

Abstract: A method comprising the steps of continuously changing the concentrations in solution of a biomacromolecule to be crystallized and a precipitant, thereby constructing a crystal phase diagram containing a solubility curve, searching for optimum conditions of crystallization on the basis of the constructed crystal phase diagram, and performing efficient growth of the crystal of the biomacromolecule. Also disclosed is an apparatus for implementing the method.

Abstract: A method for manufacturing an annular nuclear fuel pellet is provided. In the method, an annular nuclear fuel green compact whose lateral cross-section is a trapezoid is prepared. The thickness of the annular nuclear fuel green compact reduces along one direction of the central axis, and a green density of the nuclear fuel green compact increases along one direction of the central axis. The annular nuclear fuel green compact is sintered under a reducing gas atmosphere so that the annular nuclear fuel pellet is obtained. According to this method, the annular pellet which has uniform inner and outer diameters and small diametric tolerances along the pellet height is fabricated without grinding the pellet surfaces.

Abstract: A direct vessel injection (DVI) nozzle for minimum emergency core coolant (ECC) bypass is disclosed. The DVI nozzle is used in a pressurized light water reactor (PLWR) having a reactor vessel with a reactor coolant system in which a coolant flows into the reactor vessel through a cold leg and passes through a reactor core prior to being discharged to the outside of the reactor vessel through a hot leg. The DVI nozzle, provided to directly inject ECC into the reactor vessel to cool the reactor core during a break in the reactor coolant system, such as a cold leg break (CLB) that may occur in the PLWR, is placed on the reactor vessel at a position horizontally offset from the central axis of the hot leg at an angle of 10° to 30° and is involved within a region defined above the central axis of the hot leg by a distance of 1.5 times the sum of diameters of the hot leg and the DVI nozzle.

Abstract: Disclosed is a novel adsorbent for use in a 99Mo/99mTc generator, which is a medical diagnostic radioisotope generator, and in a 188W/188Re generator, which is a therapeutic radioisotope generator. The adsorbent composed of sulfated alumina or alumina-sulfated zirconia exhibits adsorption capacity superior to that of conventional adsorbents, and is stable and is thus loaded in a dry state in an adsorption column so that the radioisotope 99Mo or 188W can be adsorbed. Thus, it is possible to miniaturize the column, and such a miniaturized column is small, convenient to use, and highly efficient, and extracts a radioisotope satisfying the requirements for pharmaceuticals, and thus can be useful for radioisotope generators extracting 99mTc or 188Re.

Abstract: Disclosed is a coolant with dispersed neutron poison micro-particles, used in a supercritical water-cooled reactor (SCWR) emergency core cooling system. Since the neutron poison micro-particles are uniformly dispersed in the coolant of the emergency core cooling system for a long period time, their fluidity is not lowered even though the polarity of water is changed in a supercritical state. Therefore, the neutron poison micro-particles absorb neutrons produced from nuclear fission in a nuclear reactor core. Accordingly, the neutron poison micro-particles can be appropriately used as a means for controlling neutrons and stopping a nuclear reactor in the SCWR emergency core cooling system.

Abstract: Disclosed are therapeutic hydrogels for atopic dermatitis and a method for preparing the same. The hydrogels comprises a biocompatible polymer, a polyalcohol, and a medicinal plant extract. The hydrogels can carry medicinally effective ingredients for a sustained period of time and absorb wound exudates properly. The hydrogels have suitable gel strength and, when applied to a wound, can prevent bacterial infection of the wound. Moreover, the methods employing radiation allow the polymer chains to be crosslinked to each other, and also bring about a sterilization effect in the final hydrogel. There are no problems of toxic residues in the hydrogels. They are easy to attach to the skin and concomitantly provide a cool feeling. Supported by the laminate of hydrophilic non-woven fabric sheet and polyethylene film, the hydrogel retain water for a prolonged period of time and thus are useful in the treatment of contact dermatitis and atopic dermatitis.

Abstract: The present invention relates to a biochip for detecting phosphorylation and a method for detecting phosphorylation using the same, more precisely a biochip prepared by integrating a protein produced from the recombination of a substrate of kinase selected from the group consisting of PKC (Protein Kinase C), cdc2-PK (cdc2 Protein Kinase) and DNA-PK (DNA-dependent Protein Kinase) and the elevated protein such as Selenomonas ruminantium membrane protein on a matrix surface coated with an active group, a kit for detecting phosphorylation composed of the said biochip and a cofactor labeled with a radio-isotope and a method for detecting phosphorylation using the same. The biochip for detecting phosphorylation of the present invention using a radio-isotope facilitates the detection of phosphorylation with a minimum amount of a sample by simple processes, compared with the conventional method using an antibody.

Abstract: A system applicable to a bridge transporter telescopic servomanipulator, is provided. The bridge transporter telescopic servomanipulator is used for performing operation and maintenance of process equipments in a working environment having a possibility of radiation exposure. The system can be coupled/decoupled by including a coupling device in a telescopic transfer device and a servomanipulator, and can manipulate an ascending/descending device of the servomanipulator in a remote area without direct access by a worker. The coupling/decoupling device includes a first coupling plate and a second coupling plate, the first coupling plate being provided on a lower portion of the telescopic transfer device, and the second coupling plate being provided on an upper portion of the servomanipulator.

Abstract: This invention relates to an inhibitor of lead-induced stress corrosion cracking including nickel boride in the secondary side of steam generator tubes in nuclear power plants and an inhibition method using the same, and more particularly, to an inhibitor of lead-induced stress corrosion cracking, in which nickel boride is added to secondary side cooling water of the steam generator in an amount of 0.2˜6 g/l, and to an inhibition method using the same. According to this invention, when the inhibitor of lead-induced stress corrosion cracking is added to the secondary side of the steam generator tube in nuclear power plants, stress corrosion cracking of the tubes, which occurs in the lead-containing neutral or caustic solution, and a crack growth rate are decreased, thus increasing elongation. Further, a stress corrosion cracking ratio is decreased, and therefore the stress corrosion cracking resistance of metal or alloy can be improved.

Abstract: The present invention relates to a recombinant Escherichia coli having phbCAB originated from Alcaligenes eutrophus and an overproduction method of polyhydroxyalkanoate using the same, more precisely, a recombinant Escherichia coli ‘MG1655/pTZ18U-PHB’ or ‘JIL938/pTZ18U-PHB’ having phbCAB originated from Alcaligenes eutrophus and an overproduction method of polyhydroxyalkanoate comprising the steps of preparing transformed Escherichia coli having phbCAB originated from Alcaligenes eutrophus, inoculating and culturing the cells (growth phase), inducing the production of polyhydroxyalkanoate in the recomibnant Escherichia coli (stationary phase and producing phase), and inducing the extracellular secretion of the polyhydroxyalkanoate from the recombinant Escherichia coli.

Abstract: A water leakage-acoustic sensing method in a steam generator of a sodium-cooled fast reactor, the method including: calculating a standard deviation and an average of an octave band by octave band analysis of an input signal sound received from at least one predetermined acoustic sensor; comparing the calculated standard deviation and the calculated average of the octave band, and determining a size of the octave band based on a comparison result; calculating an average of standard deviations of the octave band recomposed by the determined size and normalizing the average of standard deviations; applying a predetermined weight, established by a predetermined neural network learning algorithm, to the normalized average of standard deviations; and generating leakage determination data based on the average of standard deviations to which the weight is applied.

Abstract: A groundwater collecting apparatus which can continuously collect groundwater, and can selectively collect groundwater at a specific depth by directly generating vertical movement is provided. The groundwater collecting apparatus includes: a vibration unit selectively admitting groundwater which exists in the monitoring well according to vibration in a vertical direction; a driving unit being supplied a power to vibrate the vibration unit in a vertical direction; and a hollow guide pipe being connected to the vibration unit to guide the groundwater to a ground, the groundwater having flowed into the vibration unit through a channel inlet of the vibration unit.

Abstract: A spacer grid used for placing and supporting fuel rods in nuclear reactor fuel assemblies is disclosed. The spacer grid of this invention has a plurality of inner strips intersecting each other to form a plurality of guide tube cells and a plurality of fuel rod cells, with a plurality of mixing blades projecting upward from the inner strips at intersections of the inner strips. The spacer grid further includes a plurality of perimeter strips to encircle the intersecting inner strips. Each of the perimeter strips is fabricated with a plurality of unit intermediate strips and a plurality of unit corner strips, with a grid spring provided on each of the unit strips.

Abstract: Disclosed herein is a fully passive decay heat removal system utilizing a partially immersed heat exchanger, the system comprising: a hot pool; an intermediate heat exchanger which heat-exchanges with the sodium of the hot pool; a cold pool; a support barrel extending vertically through the boundary between the hot pool and the cold pool; a sodium-sodium decay heat exchanger received in the support barrel; a sodium-air heat exchanger provided at a position higher than the sodium-sodium decay heat exchanger; an intermediate sodium loop connecting the sodium-sodium decay heat exchanger with the sodium-air heat exchanger; and a primary pump, wherein a portion of the effective heat transfer tube of the sodium-sodium decay heat exchanger is immersed in the cold pool, particularly in a normal operating state, and the surface of the lower end of a shroud for the sodium-sodium decay heat exchanger, the lower end being immersed in the sodium of the cold pool, has perforated holes.

Abstract: A perforated plate support supports dual-cooled fuel rods, each of which has concentric outer and inner tubes and is coupled with upper and lower end plugs at upper and lower ends thereof, and guide thimbles, each of which is used as a passage for a control rod. The perforated plate support is formed as a support plate having the shape of a flat plate, which includes internal channel holes, each of which has a diameter corresponding to an outer diameter of the inner tube, guide thimble holes, each of which has a diameter corresponding to an outer diameter of the guide thimble, and sub-channel holes around each internal channel hole. The upper or lower end of the dual-cooled fuel rod is coupled to the support plate such that the outer diameter of the inner tube is matched with the diameter of the internal channel hole.

Abstract: Disclosed is a process for recovery of uranium from a spent nuclear fuel using a carbonate solution, characterized by excellent proliferation resistance of preventing leaching of transuranium element (TRU) nuclides such as Pu, Np, Am, Cm, etc. from the spent nuclear fuel as well as environmental friendliness of minimizing waste generation, wherein a highly alkaline carbonate solution is used to separate uranium alone from the spent nuclear fuel.

Abstract: The present invention relates to an irradiation device for material test using a gamma ray radiated from a spent nuclear fuel assembly and provides the irradiation device for material test using a gamma ray radiated from a spent nuclear fuel assembly wherein an irradiation device for material test to achieve a radiation effect evaluation is manufactured to be movable upward, downward and horizontally in order to study the hardening phenomenon of the frail materials to the radiation among the atomic power facilities using a gamma ray radiated from a spent nuclear fuel assembly, thereby it is possible to adjust a position of the spent nuclear fuel used for material test using a gamma ray radiated from a spent nuclear fuel and a test material, identify a distance between the spent nuclear fuel and the test material easily with a scale and evaluate the radiation effects on the materials used at facilities handling a spent nuclear fuel under the same situation as they are really exposed.