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Jensen, C. B.*; Wachs, D. M.*; Woolstenhulme, N. E.*; Ozawa, Takayuki; Hirooka, Shun; Kato, Masato
Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Sustainable Clean Energy for the Future (FR22) (Internet), 9 Pages, 2022/04
Kajimoto, Tsuyoshi*; Shigyo, Nobuhiro*; Sanami, Toshiya*; Iwamoto, Yosuke; Hagiwara, Masayuki*; Lee, H. S.*; Soha, A.*; Ramberg, E.*; Coleman, R.*; Jensen, D.*; et al.
Nuclear Instruments and Methods in Physics Research B, 337, p.68 - 77, 2014/10
Times Cited Count:5 Percentile:38.03(Instruments & Instrumentation)The energy spectra of neutrons were measured by a time-of-flight method for 120 GeV protons on thick graphite, aluminum, copper, and tungsten targets with an NE213 scintillator at the Fermilab Test Beam Facility. Neutron energy spectra were obtained between 25 and 3000 MeV at emission angles of 30, 45, 120, and 150. The spectra were parameterized as neutron emissions from three moving sources and then compared with theoretical spectra calculated by PHITS and FLUKA codes. The yields of the theoretical spectra were substantially underestimated compared with the yields of measured spectra. The integrated neutron yields from 25 to 3000 MeV calculated with PHITS code were 16-36% of the experimental yields and those calculated with FLUKA code were 26-57% of the experimental yields for all targets and emission angles.
Sanetullaev, A.*; Tsang, M. B.*; Lynch, W. G.*; Lee, J.*; Bazin, D.*; Chan, K. P.*; Coupland, D.*; Hanzl, V.*; Hanzlova, D.*; Kilburn, M.*; et al.
Physics Letters B, 736, p.137 - 141, 2014/09
Times Cited Count:15 Percentile:69.79(Astronomy & Astrophysics)no abstracts in English
Iwamoto, Yosuke; Sanami, Toshiya*; Kajimoto, Tsuyoshi*; Shigyo, Nobuhiro*; Hagiwara, Masayuki*; Lee, H. S.*; Soha, A.*; Ramberg, E.*; Coleman, R.*; Jensen, D.*; et al.
Progress in Nuclear Science and Technology (Internet), 3, p.65 - 68, 2012/10
Neutron energy spectra at 15 and 90 produced from carbon, aluminum, copper and tungsten targets bombarded with 120-GeV protons were measured at Fermilab Test Beam Facility (FTBF) for the validation of simulation codes. The target thicknesses were 60 cm for graphite, 50 cm for aluminum, 20, 40, and 60 cm for copper and 10 cm for tungsten, respectively. The neutron time-of-flight measurements were performed using an NE213 organic liquid scintillator at 5.2 m for 90 and 8.0 m for 15 measuring from the center of the target to the surface of the detector. The raw signals (waveforms) obtained from photomultiplier tubes were recorded using the 10 bit digitizer (Agilent-acqiris DC282) with 0.5 ns sampling and 500 ns duration. To compare the experimental results, Monte Carlo calculations with the PHITS, MARS and FLUKA codes were performed. It was found that these calculated results underestimate the experimental results in the whole energy range.
Otsuka, Takaharu*; Suzuki, Toshio*; Homma, Michio*; Utsuno, Yutaka; Tsunoda, Naofumi*; Tsukiyama, Koshiro*; Hjorth-Jensen, M.*
Physical Review Letters, 104(1), p.012501_1 - 012501_4, 2010/01
Times Cited Count:358 Percentile:98.92(Physics, Multidisciplinary)no abstracts in English
Jensen, R.; Hide, Sakaguchi,*
2004 AGU Fall Meeting Abstract MR11A-0929, 0 Pages, 2004/00
Dependent upon the microstructure of a rock, different mechanical behavior and failure mechanisms have been noted in stress-induced borehole breakouts. Relatively recently, Haimson has identified a somewhat counter-intuitive material response for high-porosity rocks such as Berea Sandstone. Long, slot-like fractures emanating from the borehole, perpendicular to the maximum principal stress, were observed in laboratory samples that had been subject to far-field stresses while undergoing drilling. It has been proposed that that the failure mechanism for this phenomenon is compaction band formation in front of the crack-tip and is dependent upon the grain bonding characteristics. This paper discusses the numerical simulation of borehole breakouts in high porosity sandstones using the 3-D discrete element method (DEM) code, OpenDEM. DEM models use discrete particles that interact only with neighboring particles. Therefore, there is great advantage to using a DEM code for this type of analysis where there is dis-aggregation of material in the region of interest. This advantage stems from the formulation of assumptions inherent to DEM that are more closely aligned to the micro-structural behavior of the rock. The numerical model uses a bonded particle model where the rock is represented as a collection of randomly sized spherical particles that are densely packed and bonded together at the particle contact points. The drilling action is modeled by incrementally removing particles in the region of the borehole. Drilling fluid is not modeled. Therefore, in order to account for the flushing action of the drill fluid that carry the de-bonded sand particles from the fracture, as the DEM particles break free from the simulation matrix, they are removed from the simulation. Simulation results will be presented showing qualitative representation of the borehole breakouts.
Boyack, B. E.*; Motta, A. T.*; Peddicord, K. L.*; Alexander, C. A.*; Andersen, J. G. M.*; Blaisdell, J. A.*; Dunn, B. M.*; Ebeling-Koning, D.*; Fuketa, Toyoshi; Hache, G.*; et al.
NUREG/CR-6744, 455 Pages, 2001/12
no abstracts in English
Ozawa, Takayuki; Hirooka, Shun; Kato, Masato; Smuin, T. J.*; Jensen, C. B.*; Woolstenhulme, N. E.*; Wachs, D. M.*
no journal, ,
The ARES-MOX transient program is planned in TREAT by using MOX fuels irradiated in SPA-2 irradiation tests in EBR-II, which was conducted in 1984-1994 under the international collaboration between US and Japan, and have been stored in the current INL. The MOX fuels irradiated up to the maximum burnup of about 130 GWd/t in EBR-II includes the solid FP content of about 10 wt.%. In this program, the objectives are to acquire not only valuable data to develop the FCMI threshold for high-burnup annular MOX fuels but also knowledge about irradiation behavior of FP at transient. The overview of ARES-MOX program, schedule and outcomes expected from fuel performance calculation for annular MOX fuels irradiated in EBR-II will be introduced here.