Engineering Papers⌕ Search

SEARCH · Engineering Papers

Results for “LEU”

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.

Quote a phrase for an exact phrase match. Source license links do not imply unrestricted reuse.

At least 919 records · Page 51

Kinect Engineering with Learning (KEWL)

According to a Nielsen survey at the time of this reporting, 41% of all households have a game console. This is one market in which NASA has been absent from education and outreach efforts. Kinect Engineering with Learning (KEWL) is made to enter into that market and bring NASA education and outreach to a very familiar venue. KEWL creates an education and outreach experience that is more participatory, both in a school and museum environment. KEWL is a set of applications that runs on an Xbox 360 using the Kinect controller used for education and outreach. These applications currently include: Train R2, a visual simulation of Robonaut 2 that allows students to control a virtual R2 in a game environment; Drive R2, an interface using the Xbox 360 and Kinect controller that allows students to control the real R2 using the methods they learned playing Train R2; ISS experience, a visual tour of the interior of the International Space Station where students use their body to fly through the virtual ISS; Gravity Ball, a simulation of throwing balls in the gravity of different planets; Solar Array repair, a simulation of the simplified STS-121 solar array repair mission; and PlaySpace, a Mars/Moon application that allows students to experience different aspects of Mars/Moon. Users can "fly through" the ISS using their body, allowing an experience similar to what an astronaut would have on orbit. In PlaySpace, users can fly over the surface of Mars and view surface data obtained by Mars rovers. Users of Train R2 and Drive R2 can experience what it is like to control a robot over a distance with a time delay, simulating the time delay that would occur between ground control and an on-orbit robot. The initial ISS experiences were built using parts of code from the NASA Enigma software. The models used in these experiences were also from the Integrated Graphics Operations and Analysis Lab model database. The PlaySpace experience incorporates surface data obtained from NASA rovers and satellites and was built by NASA JPL.

Goza, Sharon↗

Heterogeneous Reactions of HNO3(g) + NaCl(s) Yields HCL(g) + NaNO3(s) and N2O5(g) + NaCl(s) Yields ClNo2(g) + NaNO3(s)

The heterogeneous reactions of HNO3(g) + NaCl(s) Yields HCL(g) + NaNO3(s) and N2O5(g) + NaCl(s) Yields ClNo2(g) + NaNO3(s)were investigated over a temperature range of 223-296 K in a flow-tube reactor coupled to a quadrupole mass spectrometer. The implications for volcanic enhancement of the HCl and HNO3 column density in the lower stratosphere are discussed.

heterogeneous↗

Laser-Based Characterization of Nuclear Fuel Plates

Ensuring the integrity of fuel-clad and clad-clad bonding in nuclear fuels is important for safe reactor operation and assessment of fuel performance, yet the measurement of bond strengths in actual fuels has proved challenging. The laser shockwave technique (LST) originally developed to characterize structural adhesion in composites is being employed to characterize interface strength in a new type of plate fuel being developed at Idaho National Laboratory (INL). LST is a non-contact method that uses lasers for the generation and detection of large-amplitude acoustic waves and is well suited for application to both fresh and irradiated nuclear-fuel plates. This paper will report on initial characterization results obtained from fresh fuel plates manufactured by different processes, including hot isostatic pressing, friction stir welding, and hot rolling.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Design Studies for a Multiple Application Thermal Reactor for Irradiation Experiments (MATRIX)

The Advanced Test Reactor (ATR) is a high power density test reactor specializing in fuel and materials irradiation. For more than 45 years, the ATR has provided irradiations of materials and fuels testing along with radioisotope production. Should unforeseen circumstances lead to the decommissioning of ATR, the U.S. Government would be left without a large-scale materials irradiation capability to meet the needs of its nuclear energy and naval reactor missions. In anticipation of this possibility, work was performed under the Laboratory Directed Research and Development (LDRD) program to investigate test reactor concepts that could satisfy the current missions of the ATR along with an expanded set of secondary missions. A survey was conducted in order to catalogue the anticipated needs of potential customers. Then, concepts were evaluated to fill the role for this reactor, dubbed the Multi-Application Thermal Reactor Irradiation eXperiments (MATRIX). The baseline MATRIX design is expected to be capable of longer cycle lengths than ATR given a particular batch scheme. The volume of test space in In-Pile-Tubes (IPTs) is larger in MATRIX than in ATR with comparable magnitude of neutron flux. Furthermore, MATRIX has more locations of greater volume having high fast neutron flux than ATR. From the analyses performed in this work, it appears that the lead MATRIX design can be designed to meet the anticipated needs of the ATR replacement reactor. However, this design is quite immature, and therefore any requirements currently met must be re-evaluated as the design is developed further.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

M5 Alloy Specification for TREAT Conceptual Fuel Cladding Selection

The Idaho National Laboratory (INL) Transient Reactor Test Facility (TREAT) is a nuclear test facility designed to provide safety data for fuel designs by simulating conditions during various types of nuclear excursions. The M5 alloy cladding material for the conceptual TREAT Low Enriched Uranium fuel core shall be supplied according to this specification.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

AGR-5/6/7 Fuel Fabrication, Process Documentation, and Disposition Planning

The need for U. S. energy self-sufficiency dictates the development of new low-cost, environmentally-safe forms of energy generation, hydrogen production and industrial heat systems using high temperature gas-cooled reactor (HTGR) technology. Efficient fabrication of ultra-high quality, coated particle fuel is a central requirement for implementing gas reactor technology. Babcock & Wilcox Nuclear Operations Group-Lynchburg (B&W NOG-L) is uniquely qualified in the U.S. with the institutional knowledge, access to equipment, and a Nuclear Regulatory Commission (NRC) license to produce tristructural isotropic (TRISO) coated particle nuclear fuel above 5 wt% 235U. This Statement of Work (SOW) defines the Subcontractor, B&W NOG-L and identifies the work scope to perform Advanced Gas Reactor (AGR)-5/6/7 fuel fabrication, process documentation, and material disposition planning.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

AGR-5/6/7 Fuel Fabrication, Process Documentation, and Disposition

The need for U. S. energy self-sufficiency dictates the development of new low-cost, environmentally-safe forms of energy generation, hydrogen production and industrial heat systems using high temperature gas-cooled reactor (HTGR) technology. Efficient fabrication of ultra-high quality, coated particle fuel is a central requirement for implementing gas reactor technology. Babcock & Wilcox Nuclear Operations Group-Lynchburg (B&W NOG-L) is uniquely qualified in the U.S. with the institutional knowledge, access to equipment, and a Nuclear Regulatory Commission (NRC) license to produce tristructural isotropic (TRISO) coated particle nuclear fuel above 5 wt% 235U. This Statement of Work (SOW) defines the Subcontractor, B&W NOG-L and identifies the work scope to perform Advanced Gas Reactor (AGR)-5/6/7 fuel fabrication, process documentation, and material disposition planning.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

AGR-5/6/7 Fuel Fabrication, Process Documentation, and Disposition

The need for U. S. energy self-sufficiency dictates the development of new low-cost, environmentally-safe forms of energy generation, hydrogen production and industrial heat systems using high temperature gas-cooled reactor (HTGR) technology. Efficient fabrication of ultra-high quality, coated particle fuel is a central requirement for implementing gas reactor technology. Babcock & Wilcox Nuclear Operations Group-Lynchburg (B&W NOG-L) is uniquely qualified in the U.S. with the institutional knowledge, access to equipment, and a Nuclear Regulatory Commission (NRC) license to produce tristructural isotropic (TRISO) coated particle nuclear fuel above 5 wt% 235U. This Statement of Work (SOW) defines the Subcontractor, B&W NOG-L and identifies the work scope to perform Advanced Gas Reactor (AGR)-5/6/7 fuel fabrication.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Method and apparatus for fabricating ceramic and metal components via additive manufacturing with uniform layered radiation drying

A freeform extrusion fabrication process for producing three-dimensional ceramic, metal and functionally gradient composite objects, including the steps of filling a plurality of paste sources with a respective plurality of aqueous paste compositions, operationally connecting respective syringes containing respective aqueous paste compositions to a mixing chamber, moving a first aqueous paste composition from a first respective paste source into the mixing chamber, moving a second aqueous paste composition from a second respective paste source into the mixing chamber, mixing the first and second aqueous paste compositions to define a first admixture having a first admixture composition, extruding the first admixture onto a surface to define an extruded layer having a first admixture composition, surrounding the sides of the extruded layer with an oil bath, radiatively drying the extruded layer.

Leu, Ming C.↗

Additively Manufactured Interdigital Filters for Ultra- Wideband Radar

Abstract— In this paper, we present the development of ultrawideband (UWB) inter-digital cavity filters manufactured with an additive technique. We employed a selective laser melting process with stainless steel via a “flipping and fixturing” approach to achieve dimensional accuracy and frequency selectivity (no postfabrication tuning) comparable to that of conventional micromachining. The filters operate at a center frequency of 3.75 GHz and 6 GHz, respectively, with an instantaneous bandwidth of 2 GHz. This paper presents design and fabrication details, a discussion of measured characteristics for both filters, and a performance comparison with respect to subtractively manufactured parts.

Keywords— Interdigital filters, UWB radar, additiv↗

Four Design Demonstration Elments (DDEs) to be irradiated in the Advanced Test Reactor (ATR) and the Belgian Reactor 2 (BR2)

The U.S. High Performance Research Reactor Conversion fuel qualification team is focused on developing and qualifying plate type uranium-molybdenum (U-Mo) monolithic and uranium silicide (U3Si4) fuel. Several irradiations of mini-plates and full-size plate irradiations will demonstrate the fuel’s behavior. Along with qualifying fuel, larger tests are planned to support licensing fuel elements. These tests are referred to as DDEs. As a result of a scoping study performed in 2018, a decision was made to irradiate two DDEs in ATR at the Idaho National Laboratory (INL) and two other DDEs in BR2 in Belgium. The objective is to demonstrate successful irradiation of each DDE to support the licensing submittal of that specific reactor. Neutronics analysis is being performed to match the power density distribution of the represented elements. Test train hardware design are being done to ensure all the target conditions are being met for the two DDEs to be irradiated.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗