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- 저자 : Wachs, Dan (검색결과 12 건)
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Modeling of Interaction Layer Growth between U-Mo Particles and an Al Matrix
김연수,G.L. Hofman,류호진,박종만,A.B. Robinson,D.M. Wachs 한국원자력학회 2013 Nuclear Engineering and Technology Vol.45 No.7
Interaction layer growth between U-Mo alloy fuel particles and Al in a dispersion fuel is a concern due to the volumeexpansion and other unfavorable irradiation behavior of the interaction product. To reduce interaction layer (IL) growth, asmall amount of Si is added to the Al. As a result, IL growth is affected by the Si content in the Al matrix. In order to predictIL growth during fabrication and irradiation, empirical models were developed. For IL growth prediction during fabrication andany follow-on heating process before irradiation, out-of-pile heating test data were used to develop kinetic correlations. Twoout-of-pile correlations, one for the pure Al matrix and the other for the Al matrix with Si addition, respectively, weredeveloped, which are Arrhenius equations that include temperature and time. For IL growth predictions during irradiation, theout-of-pile correlations were modified to include a fission-rate term to consider fission enhanced diffusion, and multiplicationfactors to incorporate the Si addition effect and the effect of the Mo content. The in-pile correlation is applicable for a pure Almatrix and an Al matrix with the Si content up to 8 wt%, for fuel temperatures up to 200 ºC, and for Mo content in the rangeof 6 – 10wt%. In order to cover these ranges, in-pile data were included in modeling from various tests, such as the USRERTR-4, -5, -6, -7 and -9 tests and Korea’s KOMO-4 test, that were designed to systematically examine the effects of thefission rate, temperature, Si content in Al matrix, and Mo content in U-Mo particles. A model converting the IL thickness tothe IL volume fraction in the meat was also developed.
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FAST irradiations and initial post irradiation examinations – Part I
Beausoleil G.,Capriotti L.,Curnutt B.,Fielding R.,Hayes S.,Wachs D. 한국원자력학회 2022 Nuclear Engineering and Technology Vol.54 No.11
The Advanced Fuels Campaign Fission Accelerated Steady-state Test (FAST) at Idaho National Laboratory (INL) completed its first irradiation cycle within the Advanced Test Reactor (ATR). The test focused on the irradiation of alloy fuel forms for use in sodium fast reactors. The first cycle of FAST testing was completed and four rodlets were removed for the initial post irradiation examination (PIE). The rodlet design and irradiation conditions were evaluated using Monte Carlo N-Particle (MCNP) for as-run power history and COMSOL for temperature analysis. These rodlets include a set of low burnups (~2.5 % fissions per initial metal atoms [%FIMA]), control rodlets, and a helium-bonded annular rodlet (4.7 %FIMA). Nondestructive PIE has been completed and includes visual inspection, neutron radiography and gamma scanning of the FAST capsules and rodlets. Radiography confirmed the integrity of the experiments, revealed that the annulus in the annular fuel was filled at a modest burnup (4.7 %FIMA), and indicated potential slumping of the cooler rodlets at lower burnup. Precision gamma scanning indicated mostly usual fission product behavior, except for cesium in the He-bonded annular fuel. Future destructive PIE will be necessary to fully interpret the effects of accelerated irradiation on U-Zr metallic fuel behavior
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Using Autonomous Robots to Enable Self-organizing Broadband Networks
Eric T. Matson,Benny Leong,Cory Q. Nguyen,Anthony Smith,Juan P. Wachs 제어로봇시스템학회 2010 제어로봇시스템학회 국제학술대회 논문집 Vol.2010 No.10
Broadband is a ubiquitous technology for connecting people together via a basic communications medium. Incorporating mobility into broadband antennas provides for the creation of movable nodes which can seek out other nodes. In contrast, stationary broadband nodes are incapable of finding new nodes if they are out of range or have an impediment. Supplying a broadband node with mobility and the capability to adapt to its environment, as well as, to other broadband nodes, is the central aim of this effort. This research enables self-organizing mobile broadband networks with the integration of broadband radios, autonomous robotic platforms and multiagent organizations. The broadband network acts as an infrastructure for external users and connects all robotic instances. The integration of these technologies furthers the ability to communicate where mobility and adaptation are critical.
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IRRADIATION PERFORMANCE OF U-Mo MONOLITHIC FUEL
Meyer, M.K.,Gan, J.,Jue, J.F.,Keiser, D.D.,Perez, E.,Robinson, A.,Wachs, D.M.,Woolstenhulme, N.,Hofman, G.L.,Kim, Y.S. Korean Nuclear Society 2014 Nuclear Engineering and Technology Vol.46 No.2
High-performance research reactors require fuel that operates at high specific power to high fission density, but at relatively low temperatures. Research reactor fuels are designed for efficient heat rejection, and are composed of assemblies of thin-plates clad in aluminum alloy. The development of low-enriched fuels to replace high-enriched fuels for these reactors requires a substantially increased uranium density in the fuel to offset the decrease in enrichment. Very few fuel phases have been identified that have the required combination of very-high uranium density and stable fuel behavior at high burnup. U-Mo alloys represent the best known tradeoff in these properties. Testing of aluminum matrix U-Mo aluminum matrix dispersion fuel revealed a pattern of breakaway swelling behavior at intermediate burnup, related to the formation of a molybdenum stabilized high aluminum intermetallic phase that forms during irradiation. In the case of monolithic fuel, this issue was addressed by eliminating, as much as possible, the interfacial area between U-Mo and aluminum. Based on scoping irradiation test data, a fuel plate system composed of solid U-10Mo fuel meat, a zirconium diffusion barrier, and Al6061 cladding was selected for development. Developmental testing of this fuel system indicates that it meets core criteria for fuel qualification, including stable and predictable swelling behavior, mechanical integrity to high burnup, and geometric stability. In addition, the fuel exhibits robust behavior during power-cooling mismatch events under irradiation at high power.
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MODELING OF INTERACTION LAYER GROWTH BETWEEN U-Mo PARTICLES AND AN Al MATRIX
Kim, Yeon Soo,Hofman, G.L.,Ryu, Ho Jin,Park, Jong Man,Robinson, A.B.,Wachs, D.M. Korean Nuclear Society 2013 Nuclear Engineering and Technology Vol.45 No.7
Interaction layer growth between U-Mo alloy fuel particles and Al in a dispersion fuel is a concern due to the volume expansion and other unfavorable irradiation behavior of the interaction product. To reduce interaction layer (IL) growth, a small amount of Si is added to the Al. As a result, IL growth is affected by the Si content in the Al matrix. In order to predict IL growth during fabrication and irradiation, empirical models were developed. For IL growth prediction during fabrication and any follow-on heating process before irradiation, out-of-pile heating test data were used to develop kinetic correlations. Two out-of-pile correlations, one for the pure Al matrix and the other for the Al matrix with Si addition, respectively, were developed, which are Arrhenius equations that include temperature and time. For IL growth predictions during irradiation, the out-of-pile correlations were modified to include a fission-rate term to consider fission enhanced diffusion, and multiplication factors to incorporate the Si addition effect and the effect of the Mo content. The in-pile correlation is applicable for a pure Al matrix and an Al matrix with the Si content up to 8 wt%, for fuel temperatures up to $200^{\circ}C$, and for Mo content in the range of 6 - 10wt%. In order to cover these ranges, in-pile data were included in modeling from various tests, such as the US RERTR-4, -5, -6, -7 and -9 tests and Korea's KOMO-4 test, that were designed to systematically examine the effects of the fission rate, temperature, Si content in Al matrix, and Mo content in U-Mo particles. A model converting the IL thickness to the IL volume fraction in the meat was also developed.
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Keiser, Dennis D. Jr.,Jue, Jan-Fong,Miller, Brandon D.,Gan, Jian,Robinson, Adam B.,Medvedev, Pavel,Madden, James,Wachs, Dan,Meyer, Mitch Korean Nuclear Society 2014 Nuclear Engineering and Technology Vol.46 No.2
In order to investigate how the microstructure of fuel/matrix-interaction (FMI) layers change during irradiation, different U-7Mo dispersion fuel plates have been irradiated to high fission density and then characterized using scanning electron microscopy (SEM). Specifially, samples from irradiated U-7Mo dispersion fuel elements with pure Al, Al-2Si and AA4043 (~4.5 wt.%Si) matrices were SEM characterized using polished samples and samples that were prepared with a focused ion beam (FIB). Features not observable for the polished samples could be captured in SEM images taken of the FIB samples. For the Al matrix sample, a relatively large FMI layer develops, with enrichment of Xe at the FMI layer/Al matrix interface and evidence of debonding. Overall, a significant penetration of Si from the FMI layer into the U-7Mo fuel was observed for samples with Si in the Al matrix, which resulted in a change of the size (larger) and shape (round) of the fission gas bubbles. Additionally, solid fission product phases were observed to nucleate and grow within these bubbles. These changes in the localized regions of the microstructure of the U-7Mo may contribute to changes observed in the macroscopic swelling of fuel plates with Al-Si matrices.
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Dennis D. Keiser,JAN-FONG JUE,BRANDON D. MILLER,JIAN GAN,ADAM B. ROBINSON,PAVEL MEDVEDEV,JAMES MADDEN,DAN WACHS,MITCH MEYER 한국원자력학회 2014 Nuclear Engineering and Technology Vol.46 No.2
In order to investigate how the microstructure of fuel/matrix-interaction (FMI) layers change during irradiation, differentU–7Mo dispersion fuel plates have been irradiated to high fission density and then characterized using scanning electronmicroscopy (SEM). Specifially, samples from irradiated U–7Mo dispersion fuel elements with pure Al, Al–2Si and AA4043(~4.5 wt.%Si) matrices were SEM characterized using polished samples and samples that were prepared with a focused ionbeam (FIB). Features not observable for the polished samples could be captured in SEM images taken of the FIB samples. Forthe Al matrix sample, a relatively large FMI layer develops, with enrichment of Xe at the FMI layer/Al matrix interface andevidence of debonding. Overall, a significant penetration of Si from the FMI layer into the U–7Mo fuel was observed forsamples with Si in the Al matrix, which resulted in a change of the size (larger) and shape (round) of the fission gas bubbles. Additionally, solid fission product phases were observed to nucleate and grow within these bubbles. These changes in thelocalized regions of the microstructure of the U–7Mo may contribute to changes observed in the macroscopic swelling of fuelplates with Al–Si matrices.
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