Gas core reactors
Fuel containment and heat transfer in gaseous core fission reactors
GASEOUS FISSION REACTOR↗
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Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.
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Gas cavity reactor simulation experiment final report
Gaseous cavitation reactor simulation experiment using uranium fluoride fuel
URANIUM FLUORIDE↗
A flow experiment on a curved porous wall gas core reactor geometry
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Lanzo, C. D.↗
Dynamic analysis of gas-core reactor system
A heat transfer analysis was incorporated into a previously developed model CODYN to obtain a model of open-cycle gaseous core reactor dynamics which can predict the heat flux at the cavity wall. The resulting model was used to study the sensitivity of the model to the value of the reactivity coefficients and to determine the system response for twenty specified perturbations. In addition, the model was used to study the effectiveness of several control systems in controlling the reactor. It was concluded that control drums located in the moderator region capable of inserting reactivity quickly provided the best control.
Turner, K. H., Jr.↗
Production of fissioning uranium plasma to approximate gas-core reactor conditions
The intense burst of neutrons from the d-d reaction in a plasma-focus apparatus is exploited to produce a fissioning uranium plasma. The plasma-focus apparatus consists of a pair of coaxial electrodes and is energized by a 25 kJ capacitor bank. A 15-g rod of 93% enriched U-235 is placed in the end of the center electrode where an intense electron beam impinges during the plasma-focus formation. The resulting uranium plasma is heated to about 5 eV. Fission reactions are induced in the uranium plasma by neutrons from the d-d reaction which were moderated by the polyethylene walls. The fission yield is determined by evaluating the gamma peaks of I-134, Cs-138, and other fission products, and it is found that more than 1,000,000 fissions are induced in the uranium for each focus formation, with at least 1% of these occurring in the uranium plasma.
Lee, J. H.↗
Thermal energy storage material thermophysical property measurement and heat transfer impact
The thermophysical properties of salts having potential for thermal energy storage to provide peaking energy in conventional electric utility power plants were investigated. The power plants studied were the pressurized water reactor, boiling water reactor, supercritical steam reactor, and high temperature gas reactor. The salts considered were LiNO3, 63LiOH/37 LiCl eutectic, LiOH, and Na2B4O7. The thermal conductivity, specific heat (including latent heat of fusion), and density of each salt were measured for a temperature range of at least + or - 100 K of the measured melting point. Measurements were made with both reagent and commercial grades of each salt.
Tye, R. P.↗
Gas core reactors for actinide transmutation and breeder applications
This work consists of design power plant studies for four types of reactor systems: uranium plasma core breeder, uranium plasma core actinide transmuter, UF6 breeder and UF6 actinide transmuter. The plasma core systems can be coupled to MHD generators to obtain high efficiency electrical power generation. A 1074 MWt UF6 breeder reactor was designed with a breeding ratio of 1.002 to guard against diversion of fuel. Using molten salt technology and a superheated steam cycle, an efficiency of 39.2% was obtained for the plant and the U233 inventory in the core and heat exchangers was limited to 105 Kg. It was found that the UF6 reactor can produce high fluxes (10 to the 14th power n/sq cm-sec) necessary for efficient burnup of actinide. However, the buildup of fissile isotopes posed severe heat transfer problems. Therefore, the flux in the actinide region must be decreased with time. Consequently, only beginning-of-life conditions were considered for the power plant design. A 577 MWt UF6 actinide transmutation reactor power plant was designed to operate with 39.3% efficiency and 102 Kg of U233 in the core and heat exchanger for beginning-of-life conditions.
Clement, J. D.↗
Pulsed Magnetic Field Driven Gas Core Reactors for Space Power & Propulsion Applications
The present results indicated that: 1. A pulsed magnetic driven fission power concept, PMD-GCR is developed for closed (NER) and semi-open (NTR) operations. 2. In power mode, power is generated at alpha less than 1 for power levels of hundreds of KW or higher 3. IN semi open NTR mode, PMD-GCR generates thrust at I(sub sp) approx. 5,000 s and jet power approx. 5KW/Kg. 4. PMD-GCR is highly subcritical and is actively driven to critically. 5. Parallel path with fusion R&D needs in many areas including magnet and plasma.
Anghaie, Samim↗
Hybrid sulfur cycle operation for high-temperature gas-cooled reactors
A hybrid sulfur (HyS) cycle process for the production of hydrogen is provided. The process uses a proton exchange membrane (PEM) SO.sub.2-depolarized electrolyzer (SDE) for the low-temperature, electrochemical reaction step and a bayonet reactor for the high-temperature decomposition step The process can be operated at lower temperature and pressure ranges while still providing an overall energy efficient cycle process.
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
Composite 3D-printed reactors for gas absorption, purification, and reaction
A composite material for gas capture, notably CO2 capture and storage. The composite material includes a mixture of a solid or liquid reactive filler and a gas-permeable polymer such that the reactive filler forms micron-scale domains in the polymer matrix.
36 MATERIALS SCIENCE↗
High Temperature Gas-cooled Reactor - History, Physics, Design Features
presentation
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
High Temperature Gas-cooled Reactor - History, Physics, Design Features
presentation
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
OSU High Temperature Test Facility Test Acceptance Report, PG-28 Low Power (<350kW) Lower Plenum Mixing Test
Test Acceptance Report for Test PG-28 at the Oregon State University High Temperature Test Facility. The purpose of this test is to investigate the impact on Lower Plenum thermal profiles and mixing due to changes in the system mass flow rate in an integral test facility scaled to General Atomics’ Modular High Temperature Gas Reactor (MHTGR) design.
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
OSU High Temperature Test Facility Test Acceptance Report, PG-29 Low Power (<350kW) Double Ended Inlet-Outlet Crossover Duct Break, Hybrid Heater
Test Acceptance Report for Test PG-29 at the Oregon State University High Temperature Test Facility. The purpose of this test is to examine the progression of the Double Ended Inlet-Outlet Crossover Duct Break transient in an integral test facility scaled to General Atomics’ Modular High Temperature Gas Reactor (MHTGR) design.
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
OSU High Temperature Test Facility Test Acceptance Report, PG-30 Low Power (<350kW) Lower Plenum Mixing, Constant Temperature Test
Test Acceptance Report for Test PG-30 at the Oregon State University High Temperature Test Facility. The purpose of this test is to investigate the impact on Lower Plenum thermal profiles and mixing due to changes in the system mass flow rate in an integral test facility scaled to General Atomics’ Modular High Temperature Gas Reactor (MHTGR) design.
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
OSU High Temperature Test Facility Test Acceptance Report, PG-31 Low Power (<350kW) Pressure Vessel Bottom Break with Restored Forced Convection Cooling Test
Test Acceptance Report for Test PG-31 at the Oregon State University High Temperature Test Facility. The purpose of this test is to examine the progression of the Pressure Vessel Bottom Break with Restored Forced Convection Cooling transient in an integral test facility scaled to General Atomics’ Modular High Temperature Gas Reactor (MHTGR) design.
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
OSU High Temperature Test Facility Test Acceptance Report PG-32 Low Power (<350kW) Asymmetric Core Heatup
Test Acceptance Report for Test PG-32 at the Oregon State University High Temperature Test Facility. The purpose of this test is to examine the facility heatup under asymmetric heating conditions in an integral test facility scaled to General Atomics’ Modular High Temperature Gas Reactor (MHGTR) design.
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗