A hybrid geothermal power system is discussed. The system includes a geothermal system including power plant (101) and pumping station (102) and a nuclear plant (103). Pumping station (102) is used to inject fluid from reservoir (104) through an injection well (105) into the bedrock (106) (also referred to as the hot dry rock HDR zone) and extracted via a secondary bore (extraction well) usually coupled to the power plant (101). In the present example however the injection well is linked to the extraction well (107). As fluid is injected into the bedrock a drop in temperature occurs due to heat transfer to the fluid. Nuclear plant (103) is utilized to combat this drop, the plant (103) has the fissionable components (1091, 1092, 1093) of the reactor positioned within bores (1081, 1082, 1083) within the HDR zone.

A hybrid geothermal power system is discussed. The system includes a geothermal system including power plant (101) and pumping station (102) and a nuclear plant (103). Pumping station (102) is used to inject fluid from reservoir (104) through an injection well (105) into the bedrock (106) (also referred to as the hot dry rock HDR zone) and extracted via a secondary bore (extraction well) usually coupled to the power plant (101). In the present example however the injection well is linked to the extraction well (107). As fluid is injected into the bedrock a drop in temperature occurs due to heat transfer to the fluid. Nuclear plant (103) is utilized to combat this drop, the plant (103) has the fissionable components (1091, 1092, 1093) of the reactor positioned within bores (1081, 1082, 1083) within the HDR zone.

One variation of a reactor assembly for a nuclear thermal propulsion system includes a set of fuel elements arranged within a moderator block. Each fuel element, in the set of fuel elements, includes: a cold shell; a compliance structure; a fuel bed; and a hot shell.

One variation of a reactor assembly for a nuclear thermal propulsion system includes a set of fuel elements arranged within a moderator block. Each fuel element, in the set of fuel elements, includes: a cold shell; a compliance structure; a fuel bed; and a hot shell.

Advances in creating carbon-free emissions continue with nuclear power. This invention aims to achieve an environment with less radioactive pollution from pebble bed reactors. This invention uses stainless steel, niobium, or ferroniobium which does not form dust like carbon pebbles. The pebble bed reactor coolant will pass over the coated pebbles and not pick up radioactive dust as in old pebble models. This new design is more complicated and costs more than current designs. However, the cleanup of a used pebble bed reactor will be far less, and the health of the workers will be greatly improved through use of this invention. This practical design will enable pebble bed reactors to become approved at a faster rate than old designs.

Advances in creating carbon-free emissions continue with nuclear power. This invention aims to achieve an environment with less radioactive pollution from pebble bed reactors. This invention uses stainless steel, niobium, or ferroniobium which does not form dust like carbon pebbles. The pebble bed reactor coolant will pass over the coated pebbles and not pick up radioactive dust as in old pebble models. This new design is more complicated and costs more than current designs. However, the cleanup of a used pebble bed reactor will be far less, and the health of the workers will be greatly improved through use of this invention. This practical design will enable pebble bed reactors to become approved at a faster rate than old designs.

The present disclosure relates to a method for monitoring failure of coated particles in fuel elements in a core of a pebble-bed high-temperature gas-cooled reactor, which is related to the technical field of nuclear reactor engineering and includes the following steps: S11, calculating an inventory of a short-lived noble gas fission nuclide; S12, obtaining a ratio of a release rate to a birth rate of the short-lived noble gas fission nuclide based on a temperature of the fuel elements using a Booth diffusion and release model; S13, deriving a theoretical expression for an activity concentration of the short-lived noble gas fission nuclide in a primary circuit using a migration model of the nuclide in the primary circuit; S14, obtaining an experimental measurement value of the activity concentration of the short-lived noble gas fission nuclide in the primary circuit at a sampling moment by gas sampling; S15, optimally calculating a failure fraction of the coated particles in the fuel elements and a share of uranium contamination in the matrix graphite in the core based on the theoretical expression and the experimental measurement value. The present disclosure can provide key parameters for the performance and status of the fuel elements in the core, which are required for radiation safety studies, source term calculations and accident analysis of the pebble-bed high-temperature gas-cooled reactor.

The present disclosure relates to a method for monitoring failure of coated particles in fuel elements in a core of a pebble-bed high-temperature gas-cooled reactor, which is related to the technical field of nuclear reactor engineering and includes the following steps: S11, calculating an inventory of a short-lived noble gas fission nuclide; S12, obtaining a ratio of a release rate to a birth rate of the short-lived noble gas fission nuclide based on a temperature of the fuel elements using a Booth diffusion and release model; S13, deriving a theoretical expression for an activity concentration of the short-lived noble gas fission nuclide in a primary circuit using a migration model of the nuclide in the primary circuit; S14, obtaining an experimental measurement value of the activity concentration of the short-lived noble gas fission nuclide in the primary circuit at a sampling moment by gas sampling; S15, optimally calculating a failure fraction of the coated particles in the fuel elements and a share of uranium contamination in the matrix graphite in the core based on the theoretical expression and the experimental measurement value. The present disclosure can provide key parameters for the performance and status of the fuel elements in the core, which are required for radiation safety studies, source term calculations and accident analysis of the pebble-bed high-temperature gas-cooled reactor.