Radiation shielding composite material can include basalt fiber and concrete. The basalt fiber can be basalt-boron fiber, basalt-gadolinium fiber, basalt-boron gadolinium fiber, or a combination thereof. The concentration can be up to about 60 kilograms per cubic meter and, in some embodiments, range from about 60 kilograms per cubic meter to about 20 kilograms per cubic meter. The basalt fiber can be formed from a basalt melt that includes up to about 20% of boron oxide, up to about 20% of gadolinium oxide, and up to about 10% of boron oxide and about 10% of gadolinium oxide. The concrete can be ordinary concrete or heavy (i.e., barite) concrete.

A migration prevention system for radioactive wastewater from an underground nuclear power plant. The underground nuclear power plant includes a nuclear island including an underground cavern group including a reactor cavity and auxiliary cavities. The migration prevention system includes a protective layer coating the reactor cavity and an impermeable layer surrounding the nuclear island. The protective layer includes an inner liner, a drainage layer, and a filling layer of rock fractures in that order. The inner liner is configured to prevent exosmosis of the radioactive wastewater of the reactor cavity. The drainage layer is configured to gather and drain seepage water. The impermeable layer is disposed in the periphery of the underground cavern group including the reactor cavity and the auxiliary cavities, and is configured to isolate the underground cavern group from natural underground water.

A migration prevention system for radioactive wastewater from an underground nuclear power plant. The underground nuclear power plant includes a nuclear island including an underground cavern group including a reactor cavity and auxiliary cavities. The migration prevention system includes a protective layer coating the reactor cavity and an impermeable layer surrounding the nuclear island. The protective layer includes an inner liner, a drainage layer, and a filling layer of rock fractures in that order. The inner liner is configured to prevent exosmosis of the radioactive wastewater of the reactor cavity. The drainage layer is configured to gather and drain seepage water. The impermeable layer is disposed in the periphery of the underground cavern group including the reactor cavity and the auxiliary cavities, and is configured to isolate the underground cavern group from natural underground water.

A method for preparing low-background cement includes: uniformly mixing a seed crystal of cement, C.sub.4AF whiskers, and high-magnesium raw material to yield a first mixture, calcining the first mixture at 1400-1500? C., to yield a low-background clinker, the first mixture including 1.0-5.0 wt. % of the seed crystal of cement, 1.0-5.0 wt. % of the C.sub.4AF whiskers, and the balance is the high-magnesium raw material; and grinding a second mixture of the low-background clinker and gypsum, to yield low-background cement. The seed crystal of cement is a high-magnesium and low hydration heat clinker, has a specific activity of Ra-226 radioactive nuclides within 50 Bq/kg, and the MgO content of the clinker is between 4.0 wt. % and 5.0 wt. %, with 50 wt. %?C.sub.3S?55.0 wt. %; and the high-magnesium raw material has a MgO content between 2.5 wt. % and 3.0 wt. %.

A radiation-shielding attenuation structure and method of forming the attenuation structure, wherein the attenuation structure is made by additively manufacturing a concrete material that includes one or more attenuation dopants configured to enhance the radiation shielding of the concrete material. The one or more attenuation dopants may be configured in the concrete material to attenuate one or more types of radiation, such as electromagnetic radiation, gamma radiation, X-ray radiation, or neutron radiation. The attenuation structure formed by the concrete material may be additively manufactured on-site according to a model that has already been pre-certified for safe or secure use, thereby providing a repeatable and reproducible process that can reduce lead times and fabrication costs. The attenuation structure may be easily modified during the additive manufacturing process to have different concrete mixtures with different attenuation characteristics, which increases the tailorability and flexibility in design of the attenuation structure.

The present invention provides a bidirectional energy-transfer system comprising: a thermally and/or electrically conductive concrete, disposed in a structural object; a location of energy supply or demand that is physically isolated from, but in thermodynamic and/or electromagnetic communication with, the thermally and/or electrically conductive concrete; and a means of transferring energy between the structural object and the location of energy supply or demand. The system can be a single node in a neural network. The thermally and/or electrically conductive concrete includes a conductive, shock-absorbing material, such as graphite. Preferred compositions are disclosed for the thermally and/or electrically conductive concrete. The bidirectional energy-transfer system may be present in a solar-energy collection system, a grade beam, an indoor radiant flooring system, a structural wall or ceiling, a bridge, a roadway, a driveway, a parking lot, a commercial aviation runway, a military runway, a grain silo, or pavers, for example.

The present invention provides a bidirectional energy-transfer system comprising: a thermally and/or electrically conductive concrete, disposed in a structural object; a location of energy supply or demand that is physically isolated from, but in thermodynamic and/or electromagnetic communication with, the thermally and/or electrically conductive concrete; and a means of transferring energy between the structural object and the location of energy supply or demand. The system can be a single node in a neural network. The thermally and/or electrically conductive concrete includes a conductive, shock-absorbing material, such as graphite. Preferred compositions are disclosed for the thermally and/or electrically conductive concrete. The bidirectional energy-transfer system may be present in a solar-energy collection system, a grade beam, an indoor radiant flooring system, a structural wall or ceiling, a bridge, a roadway, a driveway, a parking lot, a commercial aviation runway, a military runway, a grain silo, or pavers, for example.

A shielding material for shielding radioactive ray and preparation method thereof. The shielding material consists of water, a cementing material, a fine aggregate material, a coarse aggregate material and an additive, wherein the fine aggregate material consists of a borosilicate glass powder and a barite sand, and the coarse aggregate material consists of a barite. A content of boron element in the borosilicate glass powder accounts for 0.5%-1% of the total weight of the shielding material. A content of barium sulfate in the barite sand and the barite accounts for 71%-75% of the total weight of the shielding material. Other contents include water, the cementing material and the additive, and a sum of contents of all components is 100% total weight of the shielding material.

The present disclosure, in an embodiment, is a facility that includes a device configured to generate a beam having an energy range of 5 MeV to 500 MeV, a first radiation shielding wall surrounding the device, a second radiation shielding wall surrounding the first radiation shielding wall, radiation shielding fill material positioned between the first radiation shielding wall and the second radiation shielding wall forming a first barrier. In embodiments, the radiation shielding fill material includes at least fifty percent by weight of an element having an atomic number from 12 to 83, and a thickness of the first barrier is 0.5 meter to 6 meters.

The present disclosure relates to an inorganic, halogen-free flameproofing agent produced from modified, carbonized red mud (MKRS-HT) having, in some examples, a mineral composition of 10 to 50 weight % of iron compounds, 12 to 35 weight % of aluminum compounds, 5 to 17 weight % of silicon compounds, 2 to 10 weight % of titanium dioxide, 0.5 to 6 weight % of calcium compounds, the weight ratio of Fe (II) carbonate to the oxides of iron being at least 1. Examples of the agent can be used as a flame retardant in the high-temperature range. The disclosure further relates to an agent produced from modified, carbonized and rehydrated red mud, which can be used as a flame retardant in the low-temperature and high-temperature ranges, methods for producing same and use as flame retardants. The disclosure further relates to a flameproofed material system and methods for producing same.