Abstract: The present invention provides a decontamination method including the steps of decontaminating an object containing radioactive contaminated metals or alloys with a chemical decontamination agent comprising sulfuric acid (H2SO4) and forming a Ba or Sr precipitate by adding Ba or Sr cation and hydroxyl ion or halogen anion salts to the decontamination waste water. The present invention also provides a kit for decontamination including a chemical decontamination agent including sulfuric acid (H2SO4) to decontaminate an object containing radioactive contaminated metals or alloys and Ba or Sr cation and hydroxyl ion or halogen anion salts to be added to the decontamination waste water to form a precipitate.

Abstract: The present invention provides an ionic polymer membrane prepared by irradiating the compound represented by formula 1 and an ionic polymer. The ionic polymer membrane of the present invention has the advantage of excellent processability, low production costs, high ion exchange capacity and high durability. Also, the method for preparing the ionic polymer membrane of the invention not only facilitates the production of the ionic polymer membrane in a 3-dimensional network structure which has high ion exchange capacity and high dimensional stability but also makes it easy to produce membranes in various forms and sizes by using the composition itself as a coating solution with using the commercialized inexpensive ionic polymer without additional high-risk multi-step introduction process of ionic exchange group.

Abstract: Disclosed is a three-dimensional radiation detection and visualization system. The three-dimensional radiation detection and visualization system includes a first sensing module including one radiation sensor, a second sensing module including one image sensor, a first supporting body in which the first sensing module and the second sensing module are coupled to one side and the other side thereof to be vertically rotated, and a second supporting body coupled with the first supporting body so that the first supporting body is vertically rotated.

Abstract: A separate type safety injection tank comprises: a coolant injection unit connected to a reactor coolant system by a safety injection pipe such that coolant stored therein is injected into the reactor coolant system by a pressure difference from the reactor coolant system when a loss-of-coolant-accident (LOCA) occurs; a gas injection unit connected to the coolant injection unit, and configured to pressurize the coolant injected into the reactor coolant system, by introducing gas stored therein to an upper part of the coolant injection unit in the loss-of-coolant-accident; and a choking device disposed between the coolant injection unit and the gas injection unit, and configured to contract a flow cross-sectional area of the gas introduced to the coolant injection unit, and configured to maintain a flow velocity and a flow rate of the gas introduced to the coolant injection unit as a critical flow velocity and a critical flow rate when a pressure difference between the coolant injection unit and the gas inject

Abstract: Provided are an adsorbent for trapping a radioactive iodine gas generated in a process of oxidizing a nuclear fuel at a high temperature after use and a method of preparing the same, and more particularly, a radioactive iodine gas adsorbent which is formed of bismuth as a main component, thereby exhibiting an excellent radioactive iodine gas trapping capability and an excellent thermal stability after trapping, and a method of preparing the same. An adsorbent for trapping a radioactive iodine gas prepared by a method of preparing an adsorbent for trapping a radioactive iodine gas according to the present disclosure may effectively trap a radioactive iodine off-gas generated in a nuclear fuel pre-treated oxidizing process after use. Particularly, the adsorbent may trap iodine in a larger amount, which is twice or more, than a silver-containing zeolite widely used to trap a radioactive iodine gas, and the trapped iodine forms a stable compound, which is more advantageous for long-term storage.

Abstract: Disclosed herein is a method including: performing eddy current testing on a steam generator tube material by using a motorized rotating pancake coil (MRPC) probe, evaluating a test signal measured using the eddy current testing, and predicting the corrosion rate of the steam generator tube material from a noise value in the MRPC inspection signal of the steam generator tube obtained from the evaluating. When the prediction method of a corrosion rate of a steam generator tube according to the present invention is used, the steam generator tube material which has low corrosion rate can be selected at the material selecting step because the corrosion rate can be predicted and the criterions on the corrosion rate of the steam generator tube can be established as the requirements through an eddy current MRPC noise inspection of the steam generator tube material.

Abstract: The present disclosure may disclose a multi stage safety injection device, including a safety injection tank formed to contain coolant to be injected into a reactor vessel by a gravitational head of water when an accident occurs in which the pressure or water level of the reactor vessel is decreased, a pressure balance line connected to the reactor vessel and safety injection tank to form a pressure balance between the reactor vessel and the safety injection tank, and a set of safety injection lines connected to the safety injection tank and the reactor vessel to inject coolant to the reactor vessel in a pressure balance state between the reactor vessel and the safety injection tank, and connected to the safety injection tank with different heights to reduce a flow rate of coolant injected into the reactor vessel step by step according to the water level reduction of the safety injection tank in order to inject coolant to the reactor vessel at multi stages.

Abstract: Disclosed is a control rod drive mechanism. More specifically, the control rod drive mechanism includes a guide member 100 disposed in a nuclear reactor to receiving a drive shaft 2; a latch assembly 200 disposed in the guide member 100 to enable the drive shaft 2 to be withdrawn and inserted; a supporting member 300 connected to the guide member 100 to cover the drive shaft 2 and to support the latch assembly 200; and a plurality of coil housings 400 spaced apart and connected to the guide member 100 to cover the latch assembly 200, and each having a coil 410 built therein.

Abstract: The present invention provides a dry interim storage container for spent nuclear fuel, precisely a dry interim storage container that can be filled with spent nuclear fuel wherein the storage container space is also filled with metal particles. The dry storage container for spent nuclear fuel of the present invention is filled with particles in its empty space for the spent nuclear fuel, which is advantageous in cooling efficiency and maintenance cost, compared with the conventional storage method using gas.

Abstract: Disclosed herein is a method for manufacturing oxide fuel pellets. The method for manufacturing the oxide fuel pellets includes (step 1) preparing nuclear fuel powder containing uranium dioxide (UO2+x, x=0 to 0.20), (step 2) compacting the nuclear fuel powder prepared in step 1 to manufacture green pellets, sintering the green pellets manufactured in step 2 at a temperature of about 1,200° C. to about 1,400° C. by using an atmosphere gas, and reducing the green pellets sintered in step 3 at a temperature of about 800° C. to about 1,000° C. by using a reducing atmosphere gas. The method for manufacturing the oxide fuel pellets according to the present invention performs the sintering at a low temperature of about 1,200° C. to 1,400° C. to manufacture economical and safe oxide fuel pellets that are adequate for the nuclear fuel specification.

Abstract: Provided is a novel compound capable of being usefully used to diagnose and treat prostate cancer by labeling a radioisotope on a bombesin derivatives capable of selectively targeting a target material over-expressed in tumor cells in order to develop an effective diagnose and treatment method of diseases associated with prostate cancer.

Abstract: The present invention relates to a nickel-based super heat resistant alloy and a method of manufacturing the same. In the nickel-based super heat resistant alloy according to the present invention, an amount of solid solution strengthening elements (chromium, cobalt, molybdenum, or tantalum) is adjusted to improve a mechanical property, such as a creep property, at high temperatures, and aluminum or titanium is included in a predetermined amount to improve a corrosion property. The nickel-based super heat resistant alloy has excellent elongation, strength, and creep properties at normal temperature and high temperatures, and thus it is possible to manufacture parts of, by way of non-limiting example, a thermoelectric power plant, an aircraft, or a very high temperature reactor in various shapes on a large scale.

Abstract: The present invention relates to a method for manufacturing Alloy 690 ordered alloy to be used in a steam generator tube serving as a heat exchanger in a nuclear power plant (hereinafter, referred to as NPP), and Alloy 690 ordered alloy manufactured thereby, and provides a method for manufacturing Alloy 690 ordered alloy with improved thermal conductivity, and Alloy 690 ordered alloy manufactured thereby, the method comprising the steps of: solution-annealing Alloy 690; cooling the solution-annealed Alloy 690 to a first temperature of 200° C./min or less; and ordering the cooled Alloy 690 in the temperature range of 410-520° C.

Abstract: The present invention relates to a plate heat exchanger and provides a heat exchanger and a nuclear power plant comprising same, the heat exchanger comprising: a plate unit having multiple plates overlapping one another; a flow path unit, which forms flow paths having fluids flowing therein by processing at least parts of the respective plates; and a detection flow path formed between the multiple plates so as to allow the fluids leaking from the flow paths to flow thereinto and formed so as to detect the leakage of the fluids from the flow paths.

Abstract: Provided is a method of preparing a crosslinked sulfonated poly(ether ether ketone) (SPEEK) cation exchange membrane including: preparing a crosslinker mixture of a first crosslinker containing two or more vinyl oxy groups and a second crosslinker containing three or more vinyl groups; preparing a mother liquor containing the crosslinker mixture, a SPEEK polymer substituted with sodium, and a solvent; and casting the mother liquor and then irradiating radiation thereon.

Abstract: A radiation imaging device capable of matter-element information acquisition and image based selection comprises: a radiation source generating radiation; at least one scattering device receiving radiation which includes radiation transmitting a subject and scattered radiation and scattering the received radiation; and an imaging device receiving the radiation which includes the radiation transmitting the subject and the scattered radiation to measure energy and positional information so as to calculate a two-dimensional image.

Abstract: Provided are an apparatus and a method for measuring a nonlinearity parameter using laser, and more particularly, an apparatus and a method for measuring a nonlinearity parameter using laser for computing the nonlinearity parameter by irradiating laser of a toneburst signal on a surface of a sample by non-contact type laser so as to excite the sample, irradiating measurement laser beam on the surface of the sample so as to receive displacement information occurring on the surface of the sample over time, measuring the displacement in an interferometer principle, and performing a bandpass filtering for the measured signal so as to measure amplitude A1 of a component of a fundamental frequency and amplitude A2 of a component of a secondary harmonic wave.

Abstract: Disclosed are an apparatus for detecting pipe wall thinning, which measures a natural frequency of a pipe and determines a level of the pipe wall thinning, and a method thereof. The apparatus for detecting the pipe wall thinning includes a hitting member 10 for hitting the pipe T, a vibration measurement sensor 20 which measures a vibration signal generated when the pipe T is hit with the hitting member 10, and a control part 30 which compares the natural frequency calculated from the vibration signal measured from the vibration measurement sensor 20 with a natural frequency generated from a normal pipe in which wall thinning does not occur, and determines the level of the wall thinning of the pipe T.

Abstract: The present disclosure relates to a passive safety system which uses a heat exchanger together with a thermoelectric element, and a nuclear power plant comprising the same. Disclosed are a passive safety system and a nuclear power plant comprising the same, the passive safety system comprising: a heat exchanger; a thermoelectric element; and a fan unit. The heat exchanger is formed at a space inside or outside a sealed housing, and in the heat exchanger, atmosphere is introduced and heat exchange is carried out in order to lower the pressure or temperature of the atmosphere inside the housing if an accident occurs in a reactor coolant system or a secondary system disposed inside the housing.

Abstract: The present disclosure relates to a chromium-aluminum binary alloy with excellent corrosion resistance and a method of producing the same, and more particularly to a chromium-aluminum binary alloy with excellent corrosion resistance. The chromium-aluminum binary alloy may be easily produced and has ductility, thus being highly applicable as a coating material for a material requiring high-temperature corrosion resistance and wear resistance.