Patent classifications
G21D9/00
THERMAL DECOMPOSITION OF SODIUM FORMATE AND SODIUM OXALATE USING SUPER-HEATED STEAM FROM NUCLEAR REACTOR SYSTEM FOR DIRECT IN-SITU METHANOL PRODUCTION
An integrated energy system including a power plant is discussed herein. In some examples, the integrated energy system may include at least one nuclear reactor and electrical power generation system configured to generate steam and electricity, a water treatment plant configured to produce Sodium Hydroxide (NaOH) from salt water, a Sodium Formate (HCOONa) production plant configured to receive the Sodium Hydroxide (NaOH) to produce Sodium Formate (HCOONa), a Thermal Decomposition reactor configured to receive the Sodium Formate (HCOONa) and configured to receive at least a first portion of the steam or at least a second portion of the electricity from the power plant to indirectly heat the Thermal Decomposition reactor to produce Hydrogen (H.sub.2), Carbon Dioxide (CO.sub.2), and Carbon Monoxide (CO) from the Sodium Formate (HCOONa), and a Methanol (CH.sub.3OH) reaction chamber configured to receive the Hydrogen (H.sub.2), the Carbon Dioxide (CO.sub.2), and the Carbon Monoxide (CO) to produce Methanol (CH.sub.3OH).
THERMAL DECOMPOSITION OF SODIUM FORMATE AND SODIUM OXALATE USING SUPER-HEATED STEAM FROM NUCLEAR REACTOR SYSTEM FOR DIRECT IN-SITU METHANOL PRODUCTION
An integrated energy system including a power plant is discussed herein. In some examples, the integrated energy system may include at least one nuclear reactor and electrical power generation system configured to generate steam and electricity, a water treatment plant configured to produce Sodium Hydroxide (NaOH) from salt water, a Sodium Formate (HCOONa) production plant configured to receive the Sodium Hydroxide (NaOH) to produce Sodium Formate (HCOONa), a Thermal Decomposition reactor configured to receive the Sodium Formate (HCOONa) and configured to receive at least a first portion of the steam or at least a second portion of the electricity from the power plant to indirectly heat the Thermal Decomposition reactor to produce Hydrogen (H.sub.2), Carbon Dioxide (CO.sub.2), and Carbon Monoxide (CO) from the Sodium Formate (HCOONa), and a Methanol (CH.sub.3OH) reaction chamber configured to receive the Hydrogen (H.sub.2), the Carbon Dioxide (CO.sub.2), and the Carbon Monoxide (CO) to produce Methanol (CH.sub.3OH).
OLIVIA cycle: SMR reactor coupling with UCG hydrogen production for zero emission power generation in solid oxide fuel cells
This invention relates to a unique cycle for generating electricity at high efficiency and with zero carbon emissions. The cycle's fundamental energy carrier is hydrogen (H2), with H2 undergoing each unit process in the cycle either within water (H2O) molecules or as H2 gas. The heat source driving the cycle, through generation of steam, is a small nuclear reactor known in the industry as a small modular reactor (SMR). This steam's primary purpose is to provide the feed source for H2 production, which occurs in an Underground Coal Gasifier (UCG). The invention's high generation efficiency, accompanied by zero carbon emissions, derive from the UCG's steam/coal reactions and from conversion of the H2 into electricity by solid oxide fuel cells (SOFCs). These SOFCs produce, as their only waste stream, pure H2O. This H2O is then fed back for steam generation using the SMR's heat, which re-initiates the cycle. All unit processes use proven, commercially available technologies. The invention is directly applicable to any location where significant coal deposits exist.
OLIVIA cycle: SMR reactor coupling with UCG hydrogen production for zero emission power generation in solid oxide fuel cells
This invention relates to a unique cycle for generating electricity at high efficiency and with zero carbon emissions. The cycle's fundamental energy carrier is hydrogen (H2), with H2 undergoing each unit process in the cycle either within water (H2O) molecules or as H2 gas. The heat source driving the cycle, through generation of steam, is a small nuclear reactor known in the industry as a small modular reactor (SMR). This steam's primary purpose is to provide the feed source for H2 production, which occurs in an Underground Coal Gasifier (UCG). The invention's high generation efficiency, accompanied by zero carbon emissions, derive from the UCG's steam/coal reactions and from conversion of the H2 into electricity by solid oxide fuel cells (SOFCs). These SOFCs produce, as their only waste stream, pure H2O. This H2O is then fed back for steam generation using the SMR's heat, which re-initiates the cycle. All unit processes use proven, commercially available technologies. The invention is directly applicable to any location where significant coal deposits exist.
Control system and method for heat supply apparatus of nuclear power plant
Provided in the present disclosure is a control system for a heat supply apparatus of a nuclear power plant, comprising: a first-stage pressure measurement means configured for measuring a first-stage pressure of a turbine to obtain a first-stage pressure signal; a high-exhaust pressure measurement means configured for measuring an exhaust pressure of a turbine high-pressure cylinder to obtain an exhaust pressure signal; a steam extraction heating flow rate measurement means configured for measuring a steam extraction heating flow rate to obtain a steam extraction heating flow rate signal; a data acquisition module configured for acquiring and transmitting the measured first-stage pressure signal, the measured exhaust pressure signal and the measured steam extraction heating flow rate signal to a core operation processing module; the core operation processing module; and a the signal output module.
NUCLEAR FUEL DECAY HEAT UTILIZATION SYSTEM
A nuclear fuel decay heat utilization system usable for space heating in one embodiment comprises a nuclear generation plant building housing a spent fuel pool containing submerged fuel assemblies which emit decay heat that heats the pool. Plural fluidly isolated but thermally coupled heat removal systems comprising pumped flow loops operate in tandem to absorb thermal energy from the heated pool water, and transfer the thermal energy through the systems in a cascading manner form one to the next to a final external heat sink outside the plant building from which the heat is rejected to the ambient environment. A programmable controller operably regulates the intake and flowrate of water from the heat sink into the heat removal systems and monitors ambient air temperature inside to building. The flowrate is regulated to maintain a preprogrammed building setpoint air temperature by increasing fuel pool water temperature to a maximum permissible limit.
NUCLEAR FUEL DECAY HEAT UTILIZATION SYSTEM
A nuclear fuel decay heat utilization system usable for space heating in one embodiment comprises a nuclear generation plant building housing a spent fuel pool containing submerged fuel assemblies which emit decay heat that heats the pool. Plural fluidly isolated but thermally coupled heat removal systems comprising pumped flow loops operate in tandem to absorb thermal energy from the heated pool water, and transfer the thermal energy through the systems in a cascading manner form one to the next to a final external heat sink outside the plant building from which the heat is rejected to the ambient environment. A programmable controller operably regulates the intake and flowrate of water from the heat sink into the heat removal systems and monitors ambient air temperature inside to building. The flowrate is regulated to maintain a preprogrammed building setpoint air temperature by increasing fuel pool water temperature to a maximum permissible limit.
SYSTEM AND METHOD FOR LUNAR AND PLANETARY NUCLEAR REACTOR
A controlled reactor comprises a reactor core thermally coupled to one or more heat pipes and an active cooling loop. A fluid may be circulated through the active cooling loop. A heat exchanger is thermally coupled to the active cooling loop and extracts heat from the fluid as the fluid is circulated through the active cooling loop. A heating system may be provided to deliver the heat extracted by the heat exchanger to a community. A thermoelectric generator may be provided to convert heat extracted by the heat pipes to electricity for delivery to the community.
SYSTEM AND METHOD FOR LUNAR AND PLANETARY NUCLEAR REACTOR
A controlled reactor comprises a reactor core thermally coupled to one or more heat pipes and an active cooling loop. A fluid may be circulated through the active cooling loop. A heat exchanger is thermally coupled to the active cooling loop and extracts heat from the fluid as the fluid is circulated through the active cooling loop. A heating system may be provided to deliver the heat extracted by the heat exchanger to a community. A thermoelectric generator may be provided to convert heat extracted by the heat pipes to electricity for delivery to the community.
Nuclear driven carbon dioxide sequestration system and method
A system and method for heat produced at a nuclear power plant as the energy source for carbon dioxide sequestration while simultaneously producing electricity. The system includes a nuclear power plant that differs significantly from conventional designs inasmuch as its design is tightly integrated into the carbon dioxide sequestration system. The system generates electricity and sequesters carbon dioxide at the same time. Instead of simply generating electricity from the nuclear reactor and then using that electricity to run a sequestration process, the method is designed to directly provide the requisite thermal energy to the sequestration process, and simultaneously power an electrical generator. Another feature of the system design is a method of optimizing load balancing between the electrical grid and carbon dioxide sequestration.