Passive reactivity control technologies that enable reactivity control of a nuclear thermal propulsion (NTP) system with little to no active mechanical movement of circumferential control drums. By minimizing or eliminating the need for mechanical movement of the circumferential control drums during an NTP burn, the reactivity control technologies simplify controlling an NTP reactor and increase the overall performance of the NTP system. The reactivity control technologies mitigate and counteract the effects of xenon, the dominant fission product contributing to reactivity transients. Examples of reactivity control technologies include, employing burnable neutron poisons, tuning hydrogen pressure, adjusting wait time between burn cycles or merging burn cycles, and enhancement of temperature feedback mechanisms. The reactivity control technologies are applicable to low-enriched uranium NTP systems, including graphite composite fueled and tungsten ceramic and metal matrix (CERMET), or any moderated NTP system, such as highly-enriched uranium graphite composite NTP systems.

A machine, article, process of using, process of making, products produced thereby and necessary intermediates. Illustratively, there can be a process of producing electrical power, the process comprising: creating neutrons via nuclear reactions, said neutrons carrying neutron kinetic energy; moderating said neutrons to thermal energies to produce moderated neutrons, converting the neutron kinetic energy into heat, and transmitting said heat to a heat exchanger; creating ions via the nuclear reactions, stopping the ions to produce heat, and transmitting to said heat exchanger the heat generated by the stopping of the ions; capturing said moderated neutrons with sulfur atoms to produce heat, and transmitting to said heat exchanger energy released by the capturing of said moderated neutrons; transmitting energy from decaying radioisotopes created by the capturing of said moderated neutrons to said heat exchanger; heat exchanging at least some of each said heat and energy in said heat exchanger by converting water into steam; and generating electrical power with said steam.

Systems and methods suitable for capable of autonomous crack detection in surfaces by analyzing video of the surface. The systems and methods include the capability to produce a video of the surfaces, the capability to analyze individual frames of the video to obtain surface texture feature data for areas of the surfaces depicted in each of the individual frames, the capability to analyze the surface texture feature data to detect surface texture features in the areas of the surfaces depicted in each of the individual frames, the capability of tracking the motion of the detected surface texture features in the individual frames to produce tracking data, and the capability of using the tracking data to filter non-crack surface texture features from the detected surface texture features in the individual frames.

Exemplary embodiments provide automated nuclear fission reactors and methods for their operation. Exemplary embodiments and aspects include, without limitation, re-use of nuclear fission fuel, alternate fuels and fuel geometries, modular fuel cores, fast fluid cooling, variable burn-up, programmable nuclear thermostats, fast flux irradiation, temperature-driven surface area/volume ratio neutron absorption, low coolant temperature cores, refueling, and the like.

A system for transferring heat from a nuclear reactor comprises a nuclear reactor comprising a nuclear fuel and a reactor vessel surrounding the nuclear reactor and a heat transfer system surrounding the nuclear reactor. The heat transfer system comprises an inner wall surrounding the nuclear reactor vessel, first fins coupled to an outer surface of inner wall, an outer wall between the inner wall and a surrounding environment, and second fins coupled to an inner surface of the outer wall and extending in a volume between the outer surface of the inner wall and the inner surface of the outer wall, the outer surface of the inner wall and the first fins configured to transfer heat from the nuclear reactor core to the second fins and the inner surface of the outer wall by thermal radiation. The heat transfer system may be directly coupled to the nuclear reactor vessel, or may be coupled to an external reflector surrounding the nuclear reactor vessel. Related heat transfer systems and systems for selectively removing heat from a nuclear reactor are disclosed.

This invention relates to steam generators, and more particularly to horizontal steam generators for nuclear power plants with a water-water energetic reactor (VVER). We claim a horizontal nuclear power plant steam generator comprising a cylindrical vessel, two elliptical bottoms, at least one feed water supply and steam removal connection pipe, an inlet header and an outlet header, a heat-exchange tube bundle connected to the same, wherein number Ntb of heat-exchange tubes in the bundle is selected depending on outer diameter dtb of the heat exchange tubes according to formulae. The technical result of the invention is an increased heat transfer efficiency in the steam generator with a limited number and maximum length of heat exchange tubes, which allows to use tubes employed in the industry.

A system for servicing a nuclear reactor module comprises a crane operable to attach to the nuclear reactor module, wherein the crane includes provisions for routing signals from one or more sensors of the nuclear reactor module to one or more sensor receivers.

The method estimates the damaging dose of fast neutrons (dpa) which results in unacceptable degradation of paste-forming properties of steel. Upon achievement of the reactor energy yield, the direction of the coolant flow is changed from the standard direction to the reverse direction. Then an acceptable period of time is set for the annealing of reactor core elements. The temperature of the annealing mode is set and maintained by controlling the power level sufficiently to restore paste-forming properties of steel of the lower core section within the set period of time. At the end of the pre-set annealing period, the direction of the coolant flow is changed from reverse to the standard one.

A container for transporting a reactor is disclosed. The container includes a loop thermosiphon including a chamber, a heat exchanger fluidically coupled to the chamber, and an actuator including an unactuated state and an actuated state. The actuator is configured to automatically transition to the actuated state. The transition is based on an event occurring within the reactor. A working medium is configured to remove heat from the reactor in the actuated state.

Provided here is an architectural plan (the solution) for the restoration of the terminal lake, the Salton Sea, an area of prevalent geothermal sources. It includes division of the Lake into three sections, preventing pollution of the Lake from nearby farmlands and importing seawater in central section with pipeline system; providing condition for tourism, and wildlife sanctuary; generating electricity by harnessing hydro, solar, and geothermal energy; and producing potable water and lithium as byproducts. Also includes a system and method for harnessing geothermal energy for generation of electricity by using complete closed loop heat exchange systems combined with onboard drilling apparatus. The system includes several devices operating separately in many different applications in energy sectors, Also, included is alternative use for the In-Line-Pump for marine crafts propulsion.