Abstract: A nuclear power plant includes a nuclear reactor and a reactor coolant circuit containing a reactor coolant. The nuclear power plant further includes a degasification system (2) for the reactor coolant. The degasification system (2) is an ultrasonic degasification system comprising a sonotrode cluster (11) with at least one sonotrode (10) arranged in a line of the reactor coolant circuit or in a line which is fluidically connected to the reactor coolant circuit.

Abstract: Systems and techniques are described for using a robotic device to autonomously monitor activity within a property to predict a high likelihood of germ or disease transmission, and in response, perform one or more sterilization operations to regions of a property to reduce the likelihood of germ or disease transmission. In some implementations, sensor data collected by one or more sensors located within a property is processed. One or more activity patterns of a user located within the property based on processing the sensor data is identified. A determination to perform a sterilization operation based on the one or more activity patterns of the user is made. An instruction is provided to a robotic device located in the property to perform the sterilization operation.

Abstract: A nuclear reactor has an axially stratified fuel bed. The reactor features a reactor shell having a base, a top having an exhaust outlet, and an axis. The axially stratified fuel bed is within the reactor shell, and includes: a first zone configured to operate at a first temperature T1, the first zone comprising a plurality of first fuel particles, each first fuel particle comprising a first radioactive ceramic core and a first ceramic seal coating; and a second zone configured to operate at a second temperature T2, where T2>T1, the second zone comprising a plurality of second fuel particles, each second fuel particle comprising a second radioactive ceramic core and a second ceramic seal coating. A coolant fluid flow path carries a coolant fluid from the base of the reactor to the exhaust outlet, along a flow path passing sequentially through the first zone and the second zone.

Abstract: The example apparatus for testing an ultrasonic gas leak detection device includes a button configurable between an un-depressed state and a depressed state and an ultrasonic transduction device. The ultrasonic transduction device is configured to generate a first ultrasonic signal for testing the ultrasonic gas leak detection device in response to a first determination that the apparatus is in a first testing mode and that the button simultaneously corresponds to the depressed state, and generate a second ultrasonic signal for testing the ultrasonic gas leak detection device in response to a second determination that the apparatus is in a second testing mode and that the button simultaneously corresponds to the depressed state, wherein the second ultrasonic signal is different from the first ultrasonic signal.

Abstract: A steam turbine plant includes a chemical supply part configured to supply a pH adjuster to feedwater to a steam generator, an adjustment part for adjusting a supply amount of the pH adjuster to the feedwater by the chemical supply part, and at least one carbon steel component that includes a pipe or a device formed from carbon steel and through which the feedwater flows, the carbon steel component being configured such that an internal temperature at least partially falls within a range of not less than 120° C. and not greater than 180° C. under load operating condition of the steam turbine plant. The adjustment part is configured to, under the load operating condition, adjust the supply amount of the pH adjuster such that pH of the feedwater in each of the at least one carbon steel component is not less than 9.8.

Abstract: A mobile processing system is disclosed for the removal of radioactive contaminants from nuclear process waste water. The system is fully scalable, modular, and portable allowing the system to be fully customizable according the site-specific remediation requirements. It is designed to be both transported and operated from standard sized intermodal containers or custom designed enclosures for increased mobility between sites and on-site, further increasing the speed and ease with which the system may be deployed. Additionally, the system is completely modular wherein the various different modules perform different forms or stages of waste water remediation and may be connected in parallel and/or in series. Depending on the needs of the particular site, one or more different processes may be used. In some embodiments, one or more of the same modules may be used in the same operation.

Abstract: The present invention relates to a method for measuring radioactivity of radioactive waste, the method comprising an adsorption step (A) of selectively adsorbing a radioactive substance comprising at least one from among radioactive iodine and radioactive cesium from radioactive waste containing radioactive substances on an adsorption member for adsorbing a radioactive substance, and a measurement step (B) of measuring radioactivity of the radioactive substance.

Abstract: The invention is a method for treating a solid substrate, made from a first material, of metal or ceramic type, the method comprising placing the substrate in contact with a liquid metal, while the substrate is exposed to an ultrasonic wave called a power wave. At the level of a surface of the substrate, the power density is greater than a cavitation threshold of the liquid metal. Such exposure improves the wettability of the substrate surface by the liquid metal.

Abstract: An apparatus for reducing resist residue on a semiconductor substrate surface has a processing tank containing a chemical solution, and two circulation paths arranged in parallel for circulating the chemical solution inside the processing tank. Each circulation path has a pump and a filter. An ozone gas generating device supplies ozone to the processing tank. A third circulation path includes the pump and filter of one of the two circulation paths and is isolated from the processing tank and used to clean the filter by supplying ozone gas to the third circulation path.

Abstract: A method of measuring a hydrogen diffusivity of a metal structure is provided. The method includes providing a hydrogen charging surface at a first location on an external surface of the structure, and a hydrogen oxidation surface at a second location adjacent to the first location on the external surface of the structure. A hydrogen flux is generated and directed into the metal surface at the charging surface. At least a portion of the hydrogen flux generated by the charging surface and diverted back toward the surface is detected, and a transient of the diverted hydrogen flux is measured. The hydrogen diffusivity of the metal structure is then determined based on the measured transient.

Abstract: A supercritical working fluid closed cycle heat engine includes, in fluid flow series: a heat source heat exchanger configured to raise the temperature of a working fluid; an expander configured to extract work from the working fluid; a condenser configured to exchange heat between the working fluid and the cooling medium; and a separator configured to separate liquid phase working fluid from gaseous phase working fluid and deliver gaseous phase working fluid to a gaseous compressor and liquid phase working fluid to a fixed displacement liquid pump, the compressor and pump being arranged in parallel. Each of the compressor and fixed displacement pump are configured to return fluid to the heat source heat exchanger. The compressor comprises a variable inlet guide vane and a variable outlet diffuser vane.

Abstract: A tritium removal device for a lithium loop contains a neutron source (1) for colliding protons on a lithium flow, thereby generating neutrons, a lithium tank (11) for the lithium passing through this neutron source (1) to flow thereto through a flow passage (9), thereby temporarily accumulating it therein, and a lithium pump (17) for circulating and supplying the lithium of this lithium tank (11) to the neutron source (1) through a supply-side flow passage (9?). The lithium tank (11) and the lithium pump (17), into which hydrogen gas containing tritium therein can be easily collected, are enclosed within a hermetically sealed container (7) including an inactive gas therein, so that even if the hydrogen gas including the tritium therein is leaked into the hermetically sealed container (7), it is removed by a hydrogen isotope removal filter.

Abstract: A single silicon wafer micromachined thermal conduction sensor is described. The sensor consists of a heat transfer cavity with a flat bottom and an arbitrary plane shape, which is created in a silicon substrate. A heated resistor with a temperature dependence resistance is deposed on a thin film bridge, which is the top of the cavity. A heat sink is the flat bottom of the cavity and parallel to the bridge completely. The heat transfer from the heated resistor to the heat sink is modulated by the change of the thermal conductivity of the gas or gas mixture filled in the cavity. This change can be measured to determine the composition concentration of the gas mixture or the pressure of the air in a vacuum system.

Abstract: Systems passively eliminate noncondensable gasses from facilities susceptible to damage from combustion of built-up noncondensable gasses, such as H2 and O2 in nuclear power plants, without the need for external power and/or moving parts. Systems include catalyst plates installed in a lower header of the Passive Containment Cooling System (PCCS) condenser, a catalyst packing member, and/or a catalyst coating on an interior surface of a condensation tube of the PCCS condenser or an annular outlet of the PCCS condenser. Structures may have surfaces or hydrophobic elements that inhibit water formation and promote contact with the noncondensable gas. Noncondensable gasses in a nuclear power plant are eliminated by installing and using the systems individually or in combination. An operating pressure of the PCCS condenser may be increased to facilitate recombination of noncondensable gasses therein.

Abstract: A filter including a plurality of flow ducts extending in a longitudinal direction and each delimited between one pair of walls is provided. The filter includes deflectors protruding into each duct alternately from the pair of walls with overlapping in the longitudinal direction to define a zigzag shaped flow channel and provided with at least one set of holes aligned in the longitudinal direction to define through the overlapping deflectors a passage for accommodating a lower end pin of a fuel rod.

Abstract: A radiation exposure reduction method includes the steps of: injecting iron into a coolant which flows from the reactor cooling system to the reactor core in a nuclear power plant; and ferritizing and fixing radionuclides or parent nuclides thereof, which are contained in the coolant, on the surface of a reactor core structure, wherein an iron citrate which is soluble organic iron, or iron oxalate or iron fumarate which has a particle diameter of 3 ?m or less, is used as the iron to be injected into the coolant.

Abstract: A chemical decontamination reagent containing a reducing agent, a reductive metal ion, and an inorganic acid is provided to remove a radioactive oxide layer on a metal surface. The reagent can dissolve the radioactive oxide layer on the metal surface effectively at a relatively low temperature and enables a simple process of contacting the reagent to the radioactive oxide, thus economically effective in terms of cost and time required for the process. Since the decontamination does not use a conventional organic chelating agent such as oxalic acid, but the reducing agent as a main substance, the residuals of the reducing agent remained after decontamination can be decomposed and removed with an oxidizing agent. Due to the easy decomposition with the chemical decontamination reagent, secondary wastes can be minimized and the radionuclides remained in the decontamination reagent solution can be removed effectively.

Abstract: Disclosed herein is a segmental ultrasonic cleaning apparatus configured to remove scales and/or sludge deposited on a tube sheet. The segmental ultrasonic cleaning apparatus includes a plurality of segment groups arranged in a ring shape on a top surface of a tube sheet along an inner wall of the steam generator, in which each of the segment groups includes an ultrasonic element segment and a guide rail support segment loosely connected to each other by metal wires through hand holes located at a lower portion of the steam generator, such that ultrasound waves radiated from an ultrasonic transducer in each of the ultrasonic element segments travels along the surface of the tube sheet, with the segment groups tightly connected in the ring shape by tightening the metal wires via wire pulleys of flange units.

Abstract: The geometric dimensions and shape of a device for removing solid particles from the cooling medium that is circulated in the primary circuit of a nuclear reactor, in particular a boiling water nuclear reactor, are such that the device can be inserted in lieu of a fuel element or fuel assembly into an empty fuel element or assembly position of the reactor core of the nuclear reactor.

Abstract: Example embodiments are directed to upper tie plates for debris mitigation and fuel bundles that use the upper tie plates. Example embodiment tie plates may include a plurality of debris capture elements that overlap each other so as to create debris traps for particulate debris that would fall onto the fuel bundle. Example embodiment fuel bundles may use the upper tie plates for debris mitigation.

Abstract: Disclosed is an apparatus for performing an automated cleaning of nuclear fuel cladding-tubes. The apparatus comprises a pre-cleaning holding section disposed at a first side of the apparatus, a primary cleaning-material supplying section and a primary cleaning section disposed at a second side of the apparatus, a secondary cleaning section and a secondary cleaning material supplying section disposed at the second side of the apparatus and beside the primary cleaning section, an inspection section disposed at a third side of the apparatus that is opposite to the second side, and a post-cleaning holding section disposed at the fourth side of the transferring section. The pre-cleaning holding section and the post-cleaning holding section includes a cladding-tube guide where the cladding-tube is loaded before and after cleaning. Primary and secondary cleaning material supply sections are disposed at a lateral side of the primary and secondary cleaning sections respectively.

Abstract: A formic acid aqueous solution that contains Fe (II) ions is produced by dissolving metal iron in a formic acid aqueous solution. Nitrogen is supplied from a nitrogen supply device to a chemical liquid tank and then discharged from a discharge line to reduce the dissolved oxygen concentration in the aqueous solution. The chemical liquid tank is filled with the formic acid aqueous solution sealed with nitrogen, and is transferred from a factory to a nuclear reactor building designated as radiation-controlled areas. Inside the nuclear reactor building, the chemical liquid tank is installed in a film deposition apparatus connected to a reactor water recirculation pipeline. The formic acid aqueous is supplied from the chemical liquid tank to the inside of the reactor water recirculation pipeline, and then a ferrite film is formed on the inner surface of the reactor water recirculation pipeline.

Abstract: A method of suppressing deposition of radionuclides on components of a nuclear power plant comprises forming a ferrite film by contacting a first chemical including iron (II) ions, a second chemical for oxidizing the iron (II) ions to iron (III) ions, and a third chemical for adjusting the pH of a processing solution containing a mixture of the first and second chemicals to be 5.5 to 9.0 with the metal member surface in a time period from a finishing stage in decontamination step of removing contaminants formed on the surface of metal member composing the nuclear power plant, and suppressing deposition of radionuclides on the metal member by the ferrite film.

Abstract: Crystal habit modifiers (CHM) are provided to ameliorate deposit-related concerns in nuclear plant systems. The principal targets for utilization of crystal habit modifiers are Pressure Water Reactor (PWR) primary-side fuel rod crud and secondary-side steam generator deposits and Boiling Water Reactor (BWR) coolant system deposits.

Abstract: The present invention relates to a system and method for removing dissolved gas from makeup water in a water-cooled nuclear reactor. The present invention includes a storage tank for containing the makeup water that includes the dissolved gas, a membrane system positioned downstream of the storage tank to at least partially remove the dissolved gas from the makeup water; and a transport mechanism to transfer the makeup water from an outlet of the membrane system for use in the water-cooled nuclear reactor. The dissolved gas can include at least one of dissolved oxygen, dissolved nitrogen, dissolved argon and mixtures thereof.

Abstract: Systems and methods for operating an accelerator driven sub-critical core. In one embodiment, a fission power generator includes a sub-critical core and a plurality of proton beam generators. Each of the proton beam generators is configured to concurrently provide a proton beam into a different area of the sub-critical core. Each proton beam scatters neutrons within the sub-critical core. The plurality of proton beam generators provides aggregate power to the sub-critical core, via the proton beams, to scatter neutrons sufficient to initiate fission in the sub-critical core.

Abstract: A method to confine a nuclear reactor fuel bundle assembly including: inserting a lower portion of the fuel bundle assembly into an open end of a lower fuel particle barrier; supporting the lower portion of the fuel bundle with the lower fuel particle barrier; grasping the lower portion of the fuel bundle assembly with the lower fuel particle barrier; lowering an upper fuel particle barrier over an upper tie plate of the fuel bundle assembly; moving at least a portion of a handle fixed to the upper tie plate through an open slot in the upper fuel particle barrier; closing the open slot with a closure device after the handle passes through the slot, and preventing fuel particles being released from the nuclear reactor fuel bundle assembly by the upper and lower fuel particle barriers.

Abstract: This invention relates to a nuclear plant having a reactor vessel and a fluid circuit including flow path defining means, defining a flow path for circulating a reactor coolant fluid from and to the reactor vessel. The nuclear plant includes a particle collection zone defined along at least part of the length of the flow path, and particle deflection means arranged in particle deflecting relationship with the flow path to deflect particles from a fluid stream in the flow path into or toward the particle collection zone.

Abstract: A method for the surface tribological decontamination of nuclear fuel rods automates surface wiping by one or more bands of fabric. The band is distant from the axis of the rod, the rod is placed facing the band, and then the band is tensioned around the surface of the rod and moved. The rod may be immobile, moved in pure translation along its axis or with a wide-step helical movement. Preferably, the decontamination is carried by two bands simultaneously, so as to cover the total surface in one pass of the rod.

Abstract: A filtration separation method for waste resin containing highly radioactive uranium powder and device thereof is mainly used for the waste resin after water treatment process in a nuclear facility. The uranium powder contained in the waste resin is highly radioactive. Thus, prior to the treatment of the waste resin, it is necessary to filter and separate the highly radioactive uranium powder to reduce the radioactivity. It is to put the uranium powder containing waste resin into an underwater holding tank and withdraw the waste resin by an underwater pump into a uranium powder filtration box. Then the uranium powder filtration box is lifted by a hoist to move to an underwater ultrasonic cleaner. High-pressure water flushing is applied and followed by underwater ultrasonic cleaning. Then the cleaning water (containing precipitated uranium powder) from the ultrasonic cleaner is drained to uranium powder collection device.

Abstract: A debris trap catches debris falling through a fuel bundle orifice in a nuclear reactor. The debris trap includes a shaft and a debris capture tray attached to an end of the shaft. The debris capture tray includes a tray cavity sized larger than the fuel bundle orifice.

Abstract: Provided is a modified target assembly in which the target fluid is moved within the target assembly in a manner that increases the effective density of the target fluid within the beam path, thereby increasing beam yield utilizing forced convection. The target may also include optional structures, such as nozzles, diverters and deflectors for guiding and/or accelerating the flow of the target fluid. The target assembly directs the target fluid along an inner sleeve in a direction opposite the direction of the beam current to produce a counter current flow and may also direct the flow of the target fluid away from the inner surface of the inner sleeve and toward a central region in the target cavity. This countercurrent flow suppresses natural convection that tends to reduce the density of the target fluid in the beam path and tends to increase the heat transfer from the target.

Abstract: A method for the cleanup of ionic species such as cobalt and nickel in nuclear power plant aqueous streams using a sequestration resin material is disclosed herein. The method includes the steps of providing a sequestration resin for removal of radioisotopes of transition metal impurities contained in the plant process streams, and distributing the sequestration resin into the plant process streams such that the sequestration resin interacts with the process streams and removes the transition metal impurities.

Abstract: A method for cleaning an irradiated nuclear fuel assembly includes chemically enhancing a technique utilizing an apparatus including a housing adapted to engage a nuclear fuel assembly. A set of ultrasonic transducers is positioned on the housing to supply radially emanating omnidirectional ultrasonic energy to remove deposits from the nuclear fuel assembly. Any corrosion products remaining after ultrasonic fuel cleaning will have exposed surfaces that are susceptible to chemical dissolution.

Abstract: A process for selectively removing contaminant ions from a solution includes: a) contacting the solution with magnetic particles coupled to selectively chelating ion exchange functionality containing moieties prepared by: i) activating carboxyl groups on the selectively chelating ion exchange functionality containing moieties by the formation of an acyl fluoride, and ii) reacting the acyl fluoride with the magnetic particles, the magnetic particles having a particle size of less than 10 microns; b) allowing the chelating functionality coupled magnetic particles to selectively bind one or more of the contaminant ions; and, c) extracting the chelating functionality coupled magnetic particles and contaminant ions from the solution by magnetic filtration.

Abstract: The invention provides a method and tool to perform an analysis of CRUD on a nuclear fuel rod. The method recites providing a nuclear fuel rod with a layer of CRUD on an exterior of the fuel rod, scraping the CRUD from the fuel rod with a CRUD scraping tool and collecting CRUD flakes from the CRUD scraping tool. The method also provides for sorting the CRUD flakes into particle fractions, and analyzing the CRUD with a scanning electron microscope, wherein the scraping tool has a blade with a rigidity that is matched to an anticipated CRUD deposit shear strength.

Abstract: Systems and methods for servicing a fuel assembly in a light water reactor include those for controlling flow through a fuel assembly to maintain debris in the fuel assembly during removal and transportation of the fuel assembly, those for discharging debris from the fuel assembly, and those for isolating and sampling the water chemistry of a fuel assembly. An exemplary system includes a closure device configured to seal a mast to a fuel assembly to surround the upper opening of the fuel assembly and provide a flow control channel between a void in the mast and a lower opening in a lower tie plate.

Abstract: A debris trap catches debris falling through a fuel bundle orifice in a nuclear reactor. The debris trap includes a shaft and a debris capture tray attached to an end of the shaft. The debris capture tray includes a tray cavity sized larger than the fuel bundle orifice.

Abstract: The present invention relates to a method and an apparatus for suppressing adhesion of a radioactive substance, capable of suppressing adhesion of the radioactive substance onto the surface of a metallic material forming a structural member in a nuclear plant. On the surface of the metallic material forming the structural member in a nuclear power generation plant, e.g., a surface 32A of a pipe 32, an adhesion-suppressing substance 34 containing titanium oxide as a titanium compound is disposed, and a part on which the adhesion-suppressing substance 34 has been formed, is held at 80° C. or higher. The adhesion-suppressing substance 34 is formed on the surface 32A of the pipe 32 by spraying a solution or a suspension liquid of the substance.

Abstract: A method for the surface tribological decontamination of nuclear fuel rods automates surface wiping by one or more bands of fabric. The band is distant from the axis of the rod, the rod is placed facing the band, and then the band is tensioned around the surface of the rod and moved. The rod may be immobile, moved in pure translation along its axis or with a wide-step helical movement. Preferably, the decontamination is carried by two bands simultaneously, so as to cover the total surface in one pass of the rod.

Abstract: The invention relates to a process for reprocessing a spent nuclear fuel and for preparing a mixed uranium-plutonium oxide, which process comprises: a) the separation of the uranium and plutonium from the fission products, the americium and the curium that are present in an aqueous nitric solution resulting from the dissolution of the fuel in nitric acid, this step including at least one operation of coextracting the uranium and plutonium from said solution by a solvent phase; b) the partition of the coextracted uranium and plutonium to a first aqueous phase containing plutonium and uranium, and a second aqueous phase containing uranium but no plutonium; c) the purification of the plutonium and uranium that are present in the first aqueous phase; and d) a step of coconverting the plutonium and uranium to a mixed uranium/plutonium oxide. Applications: reprocessing of nuclear fuels based on uranium oxide or on mixed uranium-plutonium oxide.

Abstract: Compositions are provided that include nuclear fuel. Methods for treating nuclear fuel are provided which can include exposing the fuel to a carbonate-peroxide solution. Methods can also include exposing the fuel to an ammonium solution. Methods for acquiring molybdenum from a uranium comprising material are provided.

Abstract: It is an object of the present invention to efficiently suppress radionuclide deposition on a reactor component of nuclear power plant. Radionuclide deposition on the surface of a metallic reactor component of nuclear power plant is suppressed by forming a ferrite film on the component, wherein the film is formed, after decontamination for removing radionuclides contaminants from the component surface is completed and before the plant is started up, by contacting a treatment solution which mixes a first agent containing the iron (II) ions, a second agent for oxidizing the iron (II) ions into the iron (III) ions and a third agent for adjusting pH level of a solution to 5.5 to 9.0 in this order with the reactor component surface.

Abstract: The current methods of removing the surface-deposited layer contaminated by radioisotopes has the disadvantage of rigorous applicability conditions in such terms as the substance to be treated, the area and the shape, so the scope of their applicability is quite limited; in addition, 100% decontamination is not guaranteed and in spite of more than 50% that can be decontaminated, a greater part of the deposited radioisotopes remain unremoved, limiting the decontamination performance of the methods. Parts, structural components, etc. that have their surfaces contaminated by radioisotopes in the accelerators, nuclear reactors, RI product manufacturing factories, nuclear fuel factories, nuclear fuel reprocessing factories, etc.

Abstract: This present invention is related to a method of collecting high-level radioactive contaminated uranium powder underwater. It utilizes a long rod fixed to the pipe of the sewage pump at bottom, and takes another end of the sewage pump to connect to the sediment bag to collect uranium powder which is dispersed and contaminates the pond. Inhaling the pond water contains uranium powder into the sediment bag by sewage pump that is joined to a collecting can under it and waiting for precipitation of the powder. When the uranium powder in the sediment bag is completely precipitated into the collecting can, operator can utilize submersible pump to drain the pond water from the sediment bag. Operator may hold the cable wire of the uranium powder collecting can manually to move it to the collecting shelf and repeat the process several times until the high-level radioactive uranium powder in the contaminated pond are all collected on the uranium powder collecting shelf.

Abstract: Disclosed is an apparatus for performing an automated cleaning of nuclear fuel cladding-tubes. The apparatus comprises a pre-cleaning holding section disposed at a first side of the apparatus, a primary cleaning-material supplying section and a primary cleaning section disposed at a second side of the apparatus, a secondary cleaning section and a secondary cleaning material supplying section disposed at the second side of the apparatus and beside the primary cleaning section, an inspection section disposed at a third side of the apparatus that is opposite to the second side, and a post-cleaning holding section disposed at the fourth side of the transferring section. The pre-cleaning holding section and the post-cleaning holding section includes a cladding-tube guide where the cladding-tube is loaded before and after cleaning. Primary and secondary cleaning material supply sections are disposed at a lateral side of the primary and secondary cleaning sections respectively.

Abstract: An apparatus for cleaning an irradiated nuclear fuel assembly includes a housing adapted to engage a nuclear fuel assembly. A set of ultrasonic transducers is positioned on the housing to supply radially emanating omnidirectional ultrasonic energy to remove deposits from the nuclear fuel assembly.

Abstract: A method of suppressing deposition of radionuclides on components of a nuclear power plant comprises forming a ferrite film by contacting a first chemical including iron (II) ions, a second chemical for oxidizing the iron (II) ions to iron (III) ions, and a third chemical for adjusting the pH of a processing solution containing a mixture of the first and second chemicals to be 5.5 to 9.0 with the metal member surface in a time period from a finishing stage in decontamination step of removing contaminants formed on the surface of metal member composing the nuclear power plant, and suppressing deposition of radionuclides on the metal member by the ferrite film.

Abstract: The present invention provides a method for removing niobium-rich second-phase-particle (SPP) deposits from zirconium-niobium alloy components. The method comprises washing a freshly pickled and rinsed zirconium-niobium alloy component with an acidified oxalic acid or ammonium oxalate washing solution. The method of the present invention results in a rapid, efficient and complete removal of surface SPP deposits from the zirconium-niobium alloy component without pitting, leaving behind a clean, shiny surface without the need to use water blasting or mechanical wiping operations.

Abstract: The invention provides a method and tool to perform an analysis of CRUD on a nuclear fuel rod. The method recites providing a nuclear fuel rod with a layer of CRUD on an exterior of the fuel rod, scraping the CRUD from the fuel rod with a CRUD scraping tool and collecting CRUD flakes from the CRUD scraping tool. The method also provides for sorting the CRUD flakes into particle fractions, and analyzing the CRUD with a scanning electron microscope, wherein the scraping tool has a blade with a rigidity that is matched to an anticipated CRUD deposit shear strength.