Abstract: In a clamping jig and system for inspecting spacer grids for a nuclear fuel assembly, the jig firmly and precisely clamps a variety of grids on a measurement stage moving at high speed so that, among constituent parts of the nuclear fuel assembly, the spacer grids can be inspected using a non-contact measurer. The clamping jig includes a frame having a plurality of holding recesses into which the corresponding spacer grids are inserted, supporting means mounted in each holding recess of the frame to allow each spacer grid to be adjusted from below so it can be maintained in a horizontal state, clamping means installed around each holding recess to clamp two adjacent sides of each spacer grid to a corner of the respective holding recess, and resilient means installed on the sides opposite the clamping means and resiliently supporting the other two sides of each spacer grid.

Abstract: A method for providing a boron-lined neutron detector. The method includes providing a boron-containing material and providing water. The method includes mixing the boron-containing material into the water to create a water-based liquid mixture and providing a substrate of a cathode of the neutron detector. The method includes applying the water-based liquid mixture to the substrate of the cathode and removing water from the water-based liquid applied to the substrate to leave a boron-containing layer upon the substrate that is sensitive to neutron impingement. The step of providing a boron-containing material may be to provide the material to include B-10.

Abstract: A system for monitoring a state of a reactor core in a nuclear reactor may include an internal monitoring device located inside the reactor core, the internal monitoring device including one or more internal sensor arrays configured to take measurements of conditions of the reactor core at different vertical regions within the reactor core to generate internal measurement data; an external monitoring device located in the reactor structure outside the reactor core, the external monitoring device including one or more external sensor arrays configured to take measurements of conditions of the reactor core at positions outside the reactor core corresponding the plurality of different vertical regions within the reactor core to generate external measurement data, and a transmitter configured to wirelessly transmit the external measurement data; and a receiver station configured to determine a state of the reactor core based on the external and internal measurement data.

Abstract: A nuclear reactor comprises a pressure vessel, a nuclear reactor core comprising fissile material disposed in the pressure vessel, and a core basket disposed in the pressure vessel and containing the nuclear reactor core. An incore instrument is disposed in a guide tube of the nuclear reactor core. The incore instrument has a cable extending out of the bottom of the nuclear reactor core and making a 180° turn. A bottom support element is attached to the bottom of the core basket and defines or includes a routing tube that routes the cable of the incore instrument through the 180° turn. In some embodiments, the pressure vessel includes upper and lower vessel portions, the nuclear reactor core and core basket are disposed in the lower vessel portion, and the vessel penetration is through the lower vessel portion or through a mid-flange connecting the upper and lower vessel portions.

Abstract: A blocking device for preventing the actuation of an automatic depressurization system in a pressurized nuclear reactor system due to spurious signals resulting from a software failure. The blocking signal is removed when the coolant level within the core makeup tanks drop below a predetermined level.

Abstract: A motor operated valve diagnostic data acquisition system including: a motor operated valve assembly; a transmitter, the transmitter being permanently connected in a housing of a motor operated valve assembly; a receiver, the transmitter transmitting signals to the receiver via motor operated valve cables, the cables being existing motor operated valve cables; and electronic circuitry connected to the receiver, the electronic circuitry processing the signals received by the receiver.

Abstract: A method for modeling a nuclear reactor core that follows the history of each fuel pin and employs fuel pin flux form factors to explicitly track each fuel pin's fluence and burnup along its axial length and uses this information to obtain fundamental data for each fuel rod, i.e. fuel rod cross-sections, for each fuel pin segment. The data obtained for the fuel pins segments are employed to adjust the fuel pin flux form factors to match the real fuel pins' history so that the fuel rod power distribution can be precisely calculated based on the fuel rod cross-sections and the flux form factors.

Abstract: Example embodiments are directed to jet pump inspection apparatuses including an encoded probe driver coupled to a guide funnel. In an example embodiment, the encoded probe driver and the guide funnel are located on the body of the apparatus in order to decrease the time required for inspection, thereby limiting exposure to personnel of radioactive contamination.

Abstract: In a nuclear process control system, a priority logic module (PLM) is provided. The priority logic module comprises a plurality of input ports, each input port associated with one of a plurality of priorities, a plurality of output ports, and a test mode select port associated with a test mode select signal. The test mode select signal selects one of a normal mode or test mode, each mode being associated with matching signals received by the input ports to signals sent by the output ports. The priority logic module further comprises a configurable priority logic circuit, wherein the priority logic circuit maps one of the input ports to one of the output ports.

Abstract: In implementing an induction heating stress improvement (IHSI) method in a nuclear plant, cooling characteristic with respect to the inner surface of piping is improved by appropriate structure/layout of nozzles, and further, the cooling effect when applying IHSI to a real machine is verified by installing a thermometer, as well as air in the portion subjected to IHSI is removed by heating the piping prior to the execution of IHSI.

Abstract: A traveling reactor power monitoring system includes a probe cable, a traveling prove connected to the probe cable, a storage reel storaging the probe cable, a motor feeding and spooling the probe cable, a drive control unit driving the motor at a scheduled drive speed, a torque sensor measuring a drive torque for moving the traveling probe and the probe cable, an aimed torque DB storing a first threshold and a second threshold, a drive information DB storing the drive torque and the drive speed that the drive control unit moved the traveling probe and a scheduled drive speed processor calculating the scheduled drive speed that is set faster than previous drive speed when the previous drive torque is smaller than the second threshold, and is set slower than previous drive speed when the previous drive torque is larger than the first threshold.

Abstract: In a process for estimating the concentration (C) of a chemical element in the primary coolant of a nuclear reactor, a dilution solution or a concentrated solution of said chemical element in a predetermined concentration (C*) is injected into the primary coolant within the reactor, and the reactor includes a sensor capable of measuring a quantity (Cm) representing the concentration of said chemical element. The process is an iterative process in which repeatedly in each time step k: a stage of acquiring quantities (qdk) and (qck) representing the injected flows of dilution solution and concentrated solution in step k, and a quantity (Cmk) representing the concentration measured by the sensor; a stage of calculating an estimated value (Cek+1) of the concentration of said chemical element in the primary coolant in step k+1 on the basis of representative quantities (qdk, qck, Cmk) acquired in stage k.

Abstract: The invention relates to a method of determining at least one technological uncertainty factor in respect of nuclear fuel elements (23) as a function of variations in the production parameters of the elements (23) in relation to nominal values. The inventive method comprises a step involving the use, for at least one production parameter, of a collective variation in said parameter in relation to the nominal value within a batch of produced elements (23). The invention can be used, for example, to design, produce and check pellets for light water reactors.

Abstract: In a pressurized water reactor with all of the in-core instrumentation gaining access to the core through the reactor head, each fuel assembly in which the instrumentation is introduced is aligned with an upper internals instrumentation guide-way. In the elevations above the upper internals upper support assembly, the instrumentation is protected and aligned by upper mounted instrumentation columns that are part of the instrumentation guide-way and extend from the upper support assembly towards the reactor head in hue with a corresponding head penetration. The upper mounted instrumentation columns are supported laterally at one end by an upper guide tube and at the other end by the upper support plate.

Abstract: A method of operating a nuclear reactor is disclosed. The reactor (1) encloses a core having a plurality of fuel rods (9). Each fuel rod (9) includes a cladding and fuel pellets of a nuclear fuel. The fuel pellets are arranged in an inner space of the cladding leaving a free volume comprising an upper plenum, a lower plenum and a pellet-cladding gap. The reactor is operated at a normal power and a normal inlet sub-cooling during a normal state. The reactor is monitored for detecting a defect on the cladding of any of the fuel rods. The operation of the reactor is changed to a particular state after detecting such a defect. The particular state permits an increase of the free volume in the defect fuel rod. The reactor is operated at the particular state during a limited time period, after which the reactor is operated at the normal state.

Abstract: A robot for machining a part of structure under water, comprising a machine tool having a chamber receiving a machining element, a support and guiding structure of the machine tool fixable with respect to the part to be machined and having submersible mobile elements and corresponding submersible guiding elements defining axes along which the mobile elements are movable to position the machine tool with respect to the part to be machined, displacement units for displacement of the mobile elements along the axes, a gas supply connecting to the machine tool to inject gas in the chamber, and a programmable control unit for operating the displacement units and the machine tool based on a closed-loop control mode in order to achieve the machining of the part.

Abstract: The output of a nuclear reactor is increased by a predetermined magnitude, and the neutron beam is measured as time-series data. The temperature of the moderator in the reactor is acquired as time-series data. Time-series data on the reactivity is acquired from the time-series data on the neutron beam by the reverse dynamic characteristic method with respect to a one-point reactor kinetics equation. Time-series data on the fuel temperature of a predetermined average acquired by using the time-series data on the reactor output and a predetermined dynamic characteristic model is acquired. The reactivity feedback contribution component is determined by using the time-series data on the reactivity and the applied reactivity.

Abstract: A loose part monitoring method and system for preventing the generation of a false alarm as much as possible, including analyzing a group of detection signals that have been output from a plurality of sensors placed on a wall defining a fluid flow path, wherein the group of detection signals are analyzed for a rising gradient that is related to change in intensity of impulsive sound, a damping time that is related to change of intensity of the impulsive sound, and a frequency spectrum that is related to pitch of the impulsive sound in order to determine whether the group of detection signals are false or true.

Abstract: A water filling system for a reactor water level gauge is provided for filling a reactor water level gauge instrumentation pipe in a reactor building with water and filling the reactor water level gauge with water even in an unexpected abnormal event where the reactor building is brought into a highly radioactive environment. The water filling system for a reactor water level gauge includes a water filling instrumentation pipe guided from the reactor water level gauge instrumentation pipe in the reactor building to an outside of the reactor building and filling the reactor water level gauge instrumentation pipe in the reactor building with water even in an unexpected abnormal event of a nuclear power plant.

Abstract: An apparatus for inspecting and testing a startup range neutron monitoring system for a nuclear reactor. The apparatus includes: a neutron-flux detector; a preamplifier that amplifies an electric signal output from the neutron-flux detector; a pulse measurement unit that counts times when electric signal output from the preamplifier exceeds a discrimination voltage; a discrimination-voltage setting unit that applies the discrimination voltage to the pulse measurement unit; a voltage-setting unit that applies a voltage to the neutron-flux detector; an arithmetic processing unit that calculates an output power of the reactor based upon an output signal of the pulse measurement unit; an output unit that outputs data representing the output power of the reactor, calculated by the arithmetic processing unit; and an inspecting/testing unit that sets the discrimination voltage and the voltage to be applied by the voltage-setting unit.

Abstract: A control rod position detector including a permanent magnet that is attached on a control rod inserted in a reactor pressure vessel, where the permanent magnet is capable of moving together with the control rod, and a plurality of reed switch mechanisms that are arranged in the reactor pressure vessel at regular intervals in an insertion direction of the control rod. Each of the reed switch mechanisms is provided with a pair of reed switches that are placed so as to overlap with each other in the insertion direction of the control rod. The pair of reed switches are connected to a common wiring. The common wiring is connected to a detector that detects a position of the control rod based on signals from the reed switches.

Abstract: A method of predicting stresses on a BWR steam dryer that includes creating an analytical acoustic model of a BWR steam system; generating pressure estimations by inputting empirical data into the analytical acoustic model of the BWR steam system; creating an analytical structural model of the BWR steam dryer; and predicting stresses on the BWR steam dryer using the analytical structural model and the pressure estimations.

Abstract: A method of aligning a nuclear fuel bundle and handling selected fuel rods within the fuel bundle located in a spent fuel pool of a nuclear power plant. The bundle includes water rods, full-length and part-length fuel rods extending through a plurality of fuel spacers provided between top and bottom ends of the bundle, each spacer having a plurality of cells accommodating corresponding fuel and water rods. The method includes insertion of a rod grapple tool into a top end of a fuel bundle and down to a desired location within the bundle. A guide pin retrieval tool inserts into a side of the fuel bundle to remove a guide pin from a distal end of a gripper of the rod grapple tool, allowing the guide pin retrieval tool to grip a part-length fuel rod within the fuel bundle.

Abstract: Example embodiments of the present invention relate to a method of adjusting an oxygen concentration of a reactor water side stream in a nuclear plant. The method may include injecting demineralized water into the reactor water side stream to produce an oxygenated stream with an increased oxygen concentration. The oxygenated stream may be tested to determine the effect of a process treatment on the reactor system.

Abstract: An upper detector and a lower detector that face at least one side of a fuel assembly, on which neutrons are irradiated in a nuclear reactor, and detect radiation are set at a predetermined interval in an axial direction of the fuel assembly. Distributions of radiation signals are measured by the upper detector and the lower detector while the fuel assembly and the upper detector and the lower detectors are relatively moved along the axial direction of the fuel assembly. Soundness of radiation signals measured by the upper detector and the lower detector is determined in every measurement by comparing radiation signal distributions obtained by measuring the same portion in the axial direction of the fuel assembly in a multiplexed manner with the upper detector and the lower detector. Thereafter, relative burn-up is calculated by utilizing the measured radiation signals to measure a burn-up profile.

Abstract: A first intensity Az expressed as Az=az×E?, a first reference intensity A0 expressed as A0=a0×E?, a second intensity Bz expressed as Bz=bz×E, and a second reference intensity B0=b0×E, are evaluated. The first intensity and the first reference intensity are of radioactive nuclides generated by a neutron capture reaction of a heavy nuclide or a fission product nuclide. The second intensity and the second reference intensity are of radioactive fission product nuclides except nuclides generated by a neutron capture reaction. The reference intensities are measured where the void fraction is known. Also a correlation curve of (az/a0) and a void fraction is evaluated. Finally an axial void fraction distribution is evaluated based on the value of (az/a0) and the correlation curve.

Abstract: A method for monitoring components in a nuclear reactor is provided along with related systems and component. In one embodiment, a system is provided that includes a first transducer mechanism disposed within a nuclear reactor, the first transducer being configured to emit a first wireless signal to an identified component of the nuclear reactor. A second transducer mechanism is configured to detect a response signal that is emitted by the identified component in response to the first wireless signal. In one particular embodiment, the first transducer mechanism may include one or more confocal transducers. The confocal transducer may include two or more electrodes configured to emit their respective beams coaxially with focal points that are coincidental. The system may be configured to determine a characteristic of a component being monitored. In one particular embodiment, the component may include a fuel rod.

Abstract: An operation panel (31) having a plurality of operation switches (32, 33) operable by an operator; a control device (34) that can control driving of an A pump (36) and a B on-off valve (37) as devices in a nuclear power plant in response to an operation of the operation switch (32, 33); and a sound output device (38) that outputs a name of the A pump (36) or the B on-off valve (37) as a device corresponding to an operation switch (32, 33) selected by the operation panel (31) as sound, thereby enabling to suppress occurrence of erroneous operations in the nuclear power plant, so that highly safe operations can be ensured.

Abstract: The present invention certifies control modules of engineered safety feature instruments for a power plant automatically. The control modules can be tested before storing or operating. The test is done with enhanced testing speed and saved cost. Thus, safety of the control modules is confirmed.

Abstract: Provided are a probe and an apparatus for measuring a thickness of an oxide layer of a fuel rod, capable of testing claddings of inner and outer fuel rods of a nuclear fuel assembly without disassembling the nuclear fuel assembly. The probe includes a fuel rod transfer region on which an eddy current sensor capable of continuously testing claddings of outer fuel rods of a fixed nuclear fuel assembly is mounted. Further, the apparatus includes a frame in which a cylinder driven in upward and downward directions is mounted, a first probe connected to one side of the cylinder in order to test claddings of outer fuel rods of a nuclear fuel assembly, and a second probe connected to the other side of the cylinder in order to test claddings of inner fuel rods of the nuclear fuel assembly.

Abstract: An advanced digital rod position indication (ADRPI) system having rod drop monitoring capability. When a reactor trip occurs, the ADRPI system derives the rod drop time from the signals induced in the detector coils by the falling drive rods. The ADRPI system is linked to the reactor trip breaker to provide a reference point to allow accurate timing of the rod drop times.

Abstract: A TIP monitoring control equipment has: a process computer, a TIP control panel, and data transmitting unit. The process computer includes a operation input unit, a TIP scanning unit, a first TIP level data transmitting and receiving unit, and a TIP level data storage unit. To a first TIP level data transmitting and receiving unit, an LPRM level signal, an APRM level signal and TIP level data accumulated in the TIP control panel are input in synchronization with a TIP position signal. The TIP control panel includes a TIP driving control unit, a TIP level processing unit, a TIP position processing unit, a TIP level data accumulation unit and a second TIP level data transmitting and receiving unit. The second TIP level data transmitting and receiving unit transmits TIP level data accumulated in the TIP level data accumulation unit to the process computer via the data transmission unit.

Abstract: A working apparatus has: a working equipment for doing works on a structure; a folding/unfolding mechanism for conveying the working equipment to the working position in a folded state; a conveyance mechanism (such as a horizontal thruster) for conveying the working equipment and the folding/unfolding mechanism to the working position; a pressing mechanism (such as a ballast tank) for pressing the working equipment against the lower surface of the structure; and a traveling mechanism including a wheel for traveling along the lower surface of the structure and positioning the apparatus.

Abstract: A jet pump beam (hereinafter, referred to as a beam) is fitted into a pair of projecting portions installed to a transition piece, and after the beam is arched, a beam bolt engaged with the beam is tightened. An end of the beam bolt comes in contact with a top surface of an insert member fitted into an elbow disposed between the pair of projecting portions. An ultrasonic sensor head is fixed to the beam bolt, and ultrasonic waves are sent to the beam bolt from the ultrasonic sensor in the ultrasonic sensor head. An ultrasonic measuring apparatus obtains echo intensity of each of reflected waves generated at the end of the beam bolt and a bottom surface of the insert member, and based on the echo intensities, an echo intensity ratio R is calculated. The installed state of the beam is checked using the echo intensity ratio R.

Abstract: A dynamic port that extends from the bottom wall of an oil reservoir that surrounds the lower guide bearing of a reactor coolant pump and is in fluid communication within an oil level gauge. The dynamic port is rotatable into and out of the oil flow path to adjust the dynamic oil level shown by the oil level gauge when the pump is at operating speed to be substantially equal to the static oil level when the motor is at rest.

Abstract: The invention provides at least two electrochemical sensors positioned in a nuclear reactor or in a system adjacent to the nuclear reactor, wherein at least one of the at least two electrochemical sensors has a heated zirconium electrode, and the at least two electrochemical sensors produce voltages proportional to an electrochemical corrosion potential for a surface that each of the at least two electrochemical sensors are installed upon. The invention also provides an arrangement configured to accept the voltages produced by the at least two electrochemical sensors, wherein the arrangement is configured to determine an electrochemical corrosion potential of a zirconium fuel rod in the nuclear reactor based upon the voltages of the at least two electrochemical sensors.

Abstract: The invention provides at least two electrochemical sensors positioned in a nuclear reactor or in a system adjacent to the nuclear reactor, wherein at least one of the at least two electrochemical sensors has a heated zirconium electrode, and the at least two electrochemical sensors produce voltages proportional to an electrochemical corrosion potential for a surface that each of the at least two electrochemical sensors are installed upon. The invention also provides an arrangement configured to accept the voltages produced by the at least two electrochemical sensors, wherein the arrangement is configured to determine an electrochemical corrosion potential of a zirconium fuel rod in the nuclear reactor based upon the voltages of the at least two electrochemical sensors.

Abstract: The present invention is related to an irradiation cell for producing a radioisotope of interest through the irradiation of a target material by a particle beam, comprising a metallic insert forming a cavity designed to house the target material and to be closed by an irradiation window, wherein said metallic insert comprises at least two separate metallic parts of different materials, being composed of at least a first part comprising said cavity.

Abstract: A device for assisting in the underwater extraction or insertion of an elongate element disposed in a pipe is provided. The device includes a clamping and vibration-generating assembly including a sealed housing bearing a gripper and including a member for tightening the gripper on the pipe, an adjustable vibrator for vibrating the housing and the gripper, and a member for measuring the vibration produced by the vibrator on the pipe in order to determine the optimum vibration The device also includes a controller for remotely controlling the gripper and the vibrator. A method for assisting in the extraction or insertion of an elongate element is also provided.

Abstract: A method of calibrating a nuclear instrument using a gamma thermometer may include: measuring, in the instrument, local neutron flux; generating, from the instrument, a first signal proportional to the neutron flux; measuring, in the gamma thermometer, local gamma flux; generating, from the gamma thermometer, a second signal proportional to the gamma flux; compensating the second signal; and calibrating a gain of the instrument based on the compensated second signal. Compensating the second signal may include: calculating selected yield fractions for specific groups of delayed gamma sources; calculating time constants for the specific groups; calculating a third signal that corresponds to delayed local gamma flux based on the selected yield fractions and time constants; and calculating the compensated second signal by subtracting the third signal from the second signal. The specific groups may have decay time constants greater than 5×10?1 seconds and less than 5×105 seconds.

Abstract: A method for determining isotope ratio of fissile material having a main isotope and at least one impurity isotope, including: measurement of net areas, at respective energies, of gamma peaks of the fissile material; measurement of the reference total absorption efficiencies at the energies; calculation of the total efficiency transfers of the fissile material; and calculation of the isotope ratio of fissile material.

Abstract: Electrochemical corrosion potential (ECP) probe assemblies may be used to monitor ECP of materials due to coolant chemistry in an operating nuclear reactor. Example embodiment assemblies include at least one ECP probe that detects ECP of potentially several different materials, a structural body providing a fluid flow path for the coolant over the ECP probes, and a signal transmitter that transmits or carries ECP data to an external receiver. The ECP probes may be of any number and/or type, so as to detect ECP for different component materials, including stainless steel, a zirconium alloys, etc. The ECP probes may further detect ECP due to ion concentration, pH, etc. The ECP data may be transmitted through wired or wireless signal transmitters. Example methods include installing and using example embodiment ECP probe assemblies in nuclear reactors and facilities.

Abstract: In one embodiment, the in-bundle force measurement device includes an elongated main body, and a sensing structure disposed at a distal end of the main body. The sensing structure is configured to output a measurement indicative of force applied to the sensing structure.

Abstract: A method of absolute nuclear material assay of an unknown source comprising counting neutrons from the unknown source and providing an absolute nuclear material assay utilizing a model to optimally compare to the measured count distributions. In one embodiment, the step of providing an absolute nuclear material assay comprises utilizing a random sampling of analytically computed fission chain distributions to generate a continuous time-evolving sequence of event-counts by spreading the fission chain distribution in time.

Abstract: In a nuclear power plant, a corrosion-resistant oxide film on a surface of the metal component of a reactor structure is exposed to a high-temperature water, the corrosion-resistant oxide film containing an oxide having a property of a P-type semiconductor, and a catalytic substance having a property of an N-type semiconductor is deposited on the oxide film. The oxide film maintains the property of the P-type semiconductor.

Abstract: An apparatus generating a graphical image of a core of a boiling water reactor (BWR) using at least one data set of channel deformation data including: a computer system including a display device for presenting the graphical image and a processor generating the graphical image using the at least one data set; the graphical image of the core includes symbolic representations of control blades arranged in the core, indicia identify each control blade, and indicia regarding deformation of channels adjacent each control blade, and a viewer software tool executed by the processor which accesses the at least one data set and determines a location in the core of the control blades and channels, and correlates the deformation data with the channels for display on the graphical image.

Abstract: A method of absolute nuclear material assay of an unknown source comprising counting neutrons from the unknown source and providing an absolute nuclear material assay utilizing a model to optimally compare to the measured count distributions. In one embodiment, the step of providing an absolute nuclear material assay comprises utilizing a random sampling of analytically computed fission chain distributions to generate a continuous time-evolving sequence of event-counts by spreading the fission chain distribution in time.

Abstract: A method for collecting data regarding the operating condition of a nuclear reactor core including: positioning a first linear array of gamma thermometer (GT) sensors in a first instrument housing; positioning a second linear array of GT sensors in a second instrument housing, wherein the GT sensors are arranged asymmetrically along the linear arrays and the second linear array is asymmetrical with respect to the first linear array; positioning the first instrument housing in the reactor core at a first core location and positioning the second instrument housing at a second core location symmetrical with respect to the first core location; collecting core condition data from at least one of the GT sensors in the first linear array of GT sensors, and applying the collected core condition data as data collected from the second linear array.

Abstract: A neutron detector system for discriminating fissile material from non-fissile material wherein a digital data acquisition unit collects data at high rate, and in real-time processes large volumes of data directly into information that a first responder can use to discriminate materials. The system comprises counting neutrons from the unknown source and detecting excess grouped neutrons to identify fission in the unknown source.

Abstract: A method for determining a state of operational readiness of a fuel cell backup system of a nuclear reactor system includes monitoring a readiness state of a fuel cell system associated with a nuclear reactor system, and providing a readiness determination of the fuel cell system by comparing the monitored state of readiness of the fuel cell system to an established operating readiness state, the established operating readiness state a function of at least one characteristic of the nuclear reactor system. An apparatus includes a fuel cell monitoring system configured to monitor a readiness state of a fuel cell system associated with a nuclear reactor system, and a readiness determination system configured to provide a readiness determination of the fuel cell system by comparing the monitored state of readiness of the fuel cell system to an established operating readiness state.