New nuclear reactor concepts could help the U.S. meet its long-term climate goals, but a range of technical, regulatory, economic, and societal challenges must first be overcome. A new report provides recommendations to start laying the foundation required for advanced reactors to become a viable part of the U.S. energy system.

Google is investing in the development of the next generation of nuclear power, backing a company that’s building small modular reactors and agreeing to purchase energy once the sites start supplying US grids.

Satellite images show China working on nuclear reactor for new warship

The first ever full-scale demonstration of a nuclear reactor designed to passively cool itself in an emergency was a success, showing that it should be possible to build nuclear plants without the risk of dangerous meltdown

The California-based Middlebury Institute of International Studies published research this week that showed China has constructed a prototype nuclear reactor that could fit aboard a large surface vessel - a sign that China is making progress toward building a nuclear-powered aircraft carrier.

The post Report: China Builds ‘Prototype’ Nuclear Reactor for Aircraft Carrier appeared first on Breitbart.

It is increasingly being realised that achieving net-zero is not possible without nuclear energy

Operated by Tokyo Electric Power Company Holdings, the robot collected a fragment measuring approximately 5 millimetres in size

A new report reveals that the Kodak industrial facility in upstate New York was home to a small nuclear reactor filled with weapons-grade uranium for more than

Experts argue that the downsized power sources can provide safe, efficient energy.

A method for design of a fuel assembly for nuclear reactors, including structural components made from zirconium alloy: the mean uniaxial tensile or compressive stress to which the components are subjected during the assembly life is calculated, the zirconium alloy of which the components are made is selected according to the following criteria: those components subjected to an axial or transverse compressive stress of between −10 et −20 MPa are made from an alloy with a content of Sn between Sn=(=0.025σ−0.25)% and Sn=−0.05σ%: those components subjected to such a stress of between 0 et −10 MPa are made from an alloy the Sn content of which is between Sn=traces and Sn=(0.05σ+1)%: those components subjected to such a stress of between 0 and +10 MPa are made from an alloy the Sn content of which is between Sn=0.05% and Sn=(0.07σ+1)%: and those components subjected to such a stress of between +10 and +20 MPa are made from an alloy the content of SN of which is between 0.05% and 1.70%. A fuel assembly made according to the method.

A method for measuring the neutron flux in the core of a nuclear reactor, the method including several steps recurrently performed at instants separated by a period, the method comprising at each given instant the following steps: acquiring a total signal by a cobalt neutron detector placed inside the core of the reactor; assessing a calibration factor representative of the delayed component of the total signal due to the presence of cobalt 60 in the neutron detector; assessing a corrected signal representative of the neutron flux at the detector from the total signal and from the calibration factor; assessing a slope representative of the time-dependent change of the calibration factor between the preceding instant and the given instant; the calibration factor at the given instant being assessed as a function of the calibration factor assessed at the preceding instant, of the slope, and of the time period separating the given instant from the preceding instant.

A zirconium alloy nuclear reactor cylindrical cladding has an inner Zr substrate surface (10), an outer volume of protective material (22), and an integrated middle volume (20) of zirconium oxide, zirconium and protective material, where the protective material is applied by impaction at a velocity greater than 340 meters/second to provide the integrated middle volume (20) resulting in structural integrity for the cladding.

An integral pressurized water nuclear reactor for the production of steam utilizing a helical coil steam generator, a plurality of internal circulation pumps, and an internal control rod drive mechanism structure.

An apparatus for monitoring nuclear thermal hydraulic stability of a nuclear reactor, contains: a calculation unit configured to calculate a stability index of a nuclear thermal hydraulic phenomenon based on nuclear instrumentation signals, the signals being outputted by a plurality of nuclear instrumentation detectors placed at regular intervals in a reactor core; a simulation unit configured to simulate the nuclear thermal hydraulic phenomenon based on a physical model by using information on an operating state of the nuclear reactor as an input condition; a limit value updating unit configured to update a limit value of the nuclear thermal hydraulic phenomenon based on a result of the simulation; and a determination unit configured to determine, based on the stability index and the limit value, whether or not to activate a power oscillation suppressing device.

A pressurized water nuclear reactor (PWR) includes a once through steam generator (OTSG) disposed in a generally cylindrical pressure vessel and a divider plate spaced apart from the open end of a central riser. A sealing portion of the pressure vessel and the divider plate define an integral pressurizer volume that is separated by the divider plate from the remaining interior volume of the pressure vessel. An internal control rod drive mechanism (CRDM) has all mechanical and electromagnetomotive components including at least a motor and a lead screw disposed inside the pressure vessel. Optionally CRDM units are staggered at two or more different levels such that no two neighboring CRDM units are at the same level. Internal primary coolant pumps have all mechanical and electromagnetomotive components including at least a motor and at least one impeller disposed inside the pressure vessel. Optionally, the pumps and/or CRDM are arranged below the OTSG.

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.

A sintered fuel pellet for a water nuclear reactor fuel rod including a peripheral wall extending along a central axis and two end faces. At least one of the end faces includes at least a first chamfer extending from the peripheral wall towards the central axis with a first non-zero slope with respect to a plane perpendicular to the central axis and a second chamfer extending from the first chamfer towards the central axis with a second non-zero slope with respect to a plane perpendicular to the central axis, wherein the first slope is different from the second slope.

A pressurized water nuclear reactor (PWR) includes a once through steam generator (OTSG) disposed in a generally cylindrical pressure vessel and a divider plate spaced apart from the open end of a central riser. A sealing portion of the pressure vessel and the divider plate define an integral pressurizer volume that is separated by the divider plate from the remaining interior volume of the pressure vessel. An internal control rod drive mechanism (CRDM) has all mechanical and electromagnetomotive components including at least a motor and a lead screw disposed inside the pressure vessel. Optionally CRDM units are staggered at two or more different levels such that no two neighboring CRDM units are at the same level. Internal primary coolant pumps have all mechanical and electromagnetomotive components including at least a motor and at least one impeller disposed inside the pressure vessel. Optionally, the pumps and/or CRDM are arranged below the OTSG.

In an illustrative embodiment, a pressurized water nuclear reactor (PWR) includes a pressure vessel (12, 14, 16), a nuclear reactor core (10) disposed in the pressure vessel, and a vertically oriented hollow central riser (36) disposed above the nuclear reactor core inside the pressure vessel. A once-through steam generator (OTSG) (30) disposed in the pressure vessel includes vertical tubes (32) arranged in an annular volume defined by the central riser and the pressure vessel. The OTSG further includes a fluid flow volume surrounding the vertical tubes and having a feedwater inlet (50) and a steam outlet (52). The PWR has an operating state in which feedwater injected into the fluid flow volume at the feedwater inlet is converted to steam by heat emanating from primary coolant flowing inside the tubes of the OTSG, and the steam is discharged from the fluid flow volume at the steam outlet.

Jervis Bay one of Australia's world-renowned coastal tourist hotspots, celebrated for its idyllic white beaches, nearly became home to Australia's first nuclear power plant.

The debate over nuclear technology is a controversial one, yet many leaders in the field believe it's time for an open and calm discussion about the energy alternative.

The Justice Department announced today that General Electric Hitachi Nuclear Energy Americas LLC (GE Hitachi) has agreed to pay $2.7 million to resolve allegations under the False Claims Act that it made false statements and claims to the Department of Energy and the Nuclear Regulatory Commission (NRC) concerning an advanced nuclear reactor design.

Tons of jellyfish clog a water intake pipe at the Oskarshamn power plant in Sweden, forcing operators to shut down the reactor.

What could possibly go wrong?

Imports Intra Eu - Nuclear Reactors, Boilers, & Related Mach. in the United Kingdom decreased to 2221.38 GBP Million in February from 2328.46 GBP Million in January of 2020. Imports Intra Eu - Nuclear Reactors, Boilers, & Re in the United Kingdom averaged 1848.47 GBP Million from 1996 until 2020, reaching an all time high of 3032.87 GBP Million in March of 2019 and a record low of 923.63 GBP Million in August of 1996. This page includes a chart with historical data for the United Kingdom Imports of Intra EU - Nuclear Reactors, Boilers,.

Wildfires burning through radioactive forests in the Chernobyl Exclusion Zone in Ukraine are getting ever closer to the exploded nuclear reactor (pictured, forest fires in the famed Exclusion Zone).

Online Resource

Hayden Library - TK9212.S245 2017

Hayden Library - TK9152.F38 2017

Hayden Library - QC786.5.M375 2018

Online Resource

Hayden Library - TK9203.L5 T43 2019

£Attractive: University of Birmingham
For more latest jobs and jobs in Central England visit brightrecruits.com

Dewey Library - TK9202.I537 2019