Accelerator Production Of Tritium Project Research Articles

Solid-state high voltage modulator and its application to rf source high voltage power supplies

A solid-state high voltage modulator is described in which series-connected insulated-gate bipolar transistors (IGBTs) are switched at a fixed frequency by a pulse width modulation (PWM) regulator, that adjusts the pulse width to control the voltage out of an inductor–capacitor filter network. General Atomics proposed the HV power supply (HVPS) topology of multiple IGBT modulators connected to a common HVdc source for the large number of 1 MW klystrons in the linear accelerator of the Accelerator Production of Tritium project. The switching of 24 IGBTs to obtain 20 kVdc at 20 A for short pulses was successfully demonstrated. This effort was incorporated into the design of a −70 kV, 80 A, IGBT modulator, and in a short-pulse test 12 IGBTs regulated −5 kV at 50 A under PWM control. These two tests confirm the practicality of solid-state IGBT modulators to regulate high voltage at reasonable currents. Tokamaks such as ITER require large rf heating and current drive systems with multiple rf sources. A HVPS topology is presented that readily adapts to the three rf heating systems on ITER. To take advantage of the known economy of scale for power conversion equipment, a single HVdc source feeds multiple rf sources. The large power conversion equipment, which is located outside, converts the incoming utility line voltage directly to the HVdc needed for the class of rf sources connected to it, to further reduce cost. The HVdc feeds a set of IGBT modulators, one for each rf source, to independently control the voltage applied to each source, maximizing operational flexibility. Only the modulators are indoors, close to the rf sources, minimizing the use of costly near-tokamak floor space.

Status of materials handbooks for particle accelerator and nuclear reactor applications

In support of research and development for accelerator applications, a materials handbook was developed in August of 1998 funded by the Accelerator Production of Tritium Project. This handbook, presently called Advanced Fuel Cycle Initiative ( AFCI) Materials Handbook, Materials Data for Particle Accelerator Applications, has just issued Revision 5 and contains detailed information showing the effects of irradiation on many properties for a wide variety of materials. Development of a web-accessible materials database for Generation IV Reactor Programs has been ongoing for about three years. This handbook provides a single authoritative source for qualified materials data applicable to all Generation IV reactor concepts. A beta version of this Gen IV Materials Handbook has been completed and is presently under evaluation.

Hydrogen release from 800 MeV proton-irradiated tungsten

Tungsten irradiated in spallation neutron sources, such as those proposed for the accelerator production of tritium (APT) project, will contain large quantities of generated helium and hydrogen gas. Tungsten used in proposed fusion reactors will also be exposed to neutrons, and the generated protium will be accompanied by deuterium and tritium diffusing in from the plasma-facing surface. The release kinetics of these gases during various off-normal scenarios involving loss of coolant and after heat-induced rises in temperature are of particular interest for both applications. To determine the release kinetics of hydrogen from tungsten, tungsten rods irradiated with 800 MeV protons in the Los Alamos Neutron Science Center (LANSCE) to high exposures as part of the APT project have been examined. Hydrogen evolution from the tungsten has been measured using a dedicated mass-spectrometer system by subjecting the specimens to an essentially linear temperature ramp from ∼300 to ∼1500 K. Release profiles are compared with predictions obtained using the Tritium Migration Analysis Program (TMAP4). The measurements show that for high proton doses, the majority of the hydrogen is released gradually, starting at about 900 K and reaching a maximum at about 1400 K, where it drops fairly rapidly. Comparisons with TMAP show quite reasonable agreement using a trap energy of 1.4 eV and a trap density of ∼7%. There is a small additional release fraction occurring at ∼550 K, which is believed to be associated with low-energy trapping at or near the surface, and, therefore, was not included in the bulk TMAP model.

Vaporization of elemental mercury from molten lead at low concentrations

Experiments were conducted to measure the rate of vaporization of elemental mercury from molten lead to provide a basis for estimating radiological source terms for the APT (Accelerator Production of Tritium project) lead blanket. These data also have application to other accelerator targets in which mercury may be created by proton spallation in lead. Molten pools of lead with from 0.01% to 0.10% mercury were prepared under inert conditions. Experiments were conducted which varied in duration from several hours to as long as a month to measure the mercury vaporization from the lead pools. The melt pools and gas atmospheres were controlled at 340 degrees C during the tests, above the melting temperature of lead. Parameters which were varied in the tests included the mercury concentrations, gas flow rates over the melt, circulation in the melts, gas atmosphere compositions and the addition of aluminum to the melts. The vaporization of mercury was found to scale roughly linearly with the concentration of mercury in the pool. Variations in the gas flow rates were not found to have any effect on the mass transfer, however circulation of the melt by a submerged stirrer did enhance the mercury vaporization rate. The rate of mercury vaporization under a high-purity argon atmosphere was found to exceed that for an air atmosphere by as much as a factor of from ten to 20; the causal factor in this variation was the formation of an oxide layer over the melt pool with the air atmosphere which retarded mass transfer across the melt-atmosphere interface. Aluminum was introduced into the melt to investigate its effect upon the mercury vaporization rate. No effect was observed for a case under a high-purity argon atmosphere, which suggests that there are no chemical effects of the aluminum on the vaporization kinetics. With an air atmosphere, the presence of aluminum in the melt reduced the mercury vaporization by a factor of six in comparison to the identical test but without aluminum, suggesting that aluminum in the lead/ mercury melt retards the vaporization of mercury by creating a surface oxide layer in addition to the lead-oxide layer or by changing the character of the lead-oxide layer, thereby increasing the mass transfer resistance.

The effect of coatings on deuterium retention and permeation in aluminum 6061-T6 APT tritium production tubes

The accelerator production of tritium project will utilize spallation neutrons incident on thousands of 3 He gas filled metal tubes to produce tritium by way of the exothermic 3 He(n,p) 3 H reaction. Tritons with energies up to 192 keV and protons with energies up to 576 keV are directly implanted into the tube walls. To minimize tritium retention in the tubes and permeation into the coolant surrounding the tubes, it is desirable to have the implanted tritium migrate back to the inner surface of the tubes and rapidly recombine to be released as T 2 and HT. Aluminum alloy (Al 6061-T6) is the primary candidate material for fabrication of the tubes. Aluminum alloy samples implanted with deuterons and protons to fluences as high as 3×10 22 D (and p)/m 2 were studied. Deuterium retention was measured by mass spectrometry during thermal desorption. Approximately 10% of the implanted deuterium was retained. Copper, nickel and anodized coatings on aluminum alloy were studied as possible methods of reducing retention and permeation of the tritium. In these experiments, the Cu and Ni coatings reduced the retention significantly, whereas retention increased in the anodized coated sample.

Hydrogen release from 800 MeV proton-irradiated tungsten rods

For the Accelerator Production of Tritium Project (APT), spallation neutrons will be moderated and then absorbed in 3He gas to produce tritium. The spallation neutrons will be generated by the interaction of high energy (~1 GeV) protons with solid tungsten rods or cylinders. A byproduct of the spallation reactions is large amounts of helium and hydrogen gas generated in the rods and other structural materials. The release kinetics of these gases during various proposed off-normal scenarios involving loss of coolant and afterheat-induced rises in temperature is of particular interest to the APT Project. In addition, however, this data is of interest for fusion reactors where tungsten used in a tokamak divertor will also be exposed to neutrons. In this case, the generated protium will be accompanied by deuterium and tritium diffusing in from the plasma-facing surface. Tungsten rods irradiated with 800 MeV protons in the Los Alamos Neutron Science Center (LANCE) to high exposures have been sectioned to produce small specimens suitable for measurement of both hydrogen and helium. Hydrogen evolution was measured by subjecting the specimens to a simulated temperature ramp from ~200 to ~1200°C, similar to that expected due to a loss of coolant and subsequent afterheat. The release measurements were conducted using mass spectrometric techniques. Four release peaks at temperatures of approximately 550, 850, 1100 and 1200°C were observed, initially suggesting a number of trapping sites with different binding energies. Subsequent analysis, however, showed that the observed peaks were artifacts of the temperature heating profile, and that the release curve could be duplicated using a single trap energy of 1.4 eV.

Materials Selection and Qualification Processes at a High-Power Spallation Neutron Source

The accelerator at the Los Alamos Neutron Science Center (LANSCE) at the Los Alamos National Laboratory has been in operation since 1972. Development of materials for service in high voltage applications, high-vacuum systems, magnetic and electric fields, high particle radiation fluxes, and corrosive atmospheres has been ongoing during this period. Materials were initially selected based on performance at other facilities and at fission reactors. Modification to materials selection and specifications were made based on experience at LANSCE. Plans for higher power accelerators, such as the one proposed for the Accelerator Production of Tritium Project, have led to a realization that dedicated materials radiation damage effects studies are necessary to ensure adequate service lifetimes and to allow planning for preventative maintenance. Published by Elsevier Science Inc.