Gamma-gamma density measurements: basic response and environmental corrections

Minette, Daniel C.; Gilchrist, W.A.; Hübner, B.

doi:10.1109/23.34631

Cited by 3 publications

(1 citation statement)

References 4 publications

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“…The exact energy range and the number of energy channels spanning it vary with individual tool design. The near-spaced detector provides additional information, which is used in petroleum applications to correct for mudcake on the side of the borehole (Minette et al 1989), and it may be useful for correcting for casing and air gap at the Hanford Site. The tools also measure counts in both detectors at lower energies of about 40 to 80 keV, each tool design having its own specific energy limits and channels.…”

Section: Density Logging Toolsmentioning

confidence: 99%

Calibration models for density borehole logging - construction report

Engelmann¹,

Lewis²,

Stromswold³

1995

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Section: Density Logging Toolsmentioning

confidence: 99%

Calibration models for density borehole logging - construction report

Engelmann¹,

Lewis²,

Stromswold³

1995

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Modelling the spatial response of a compensated density tool

Petler¹

1990

IEEE Trans. Nucl. Sci.

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MCNP capabilities for nuclear well logging calculations

Forster

Little

Briesmeister

et al. 1990

IEEE Trans. Nucl. Sci.

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The La Alamcm Radiation 'IY~sport Code System (LARTCS) coneiatrr of stateof-th~art Monte Carlo and discrete ordinatee transport codes and data libraries, The general-purpose continuou~energy Monte Carlo code MCNP (Monte @lo Neutron~hoton), part of the LARTCS, provides a computational predictive capability for many applications of interest to the nuc!ear well logging community. The generalized three-dimensional geometry of h4CN P ia well suited for bor ehole-tool modelm SA B-RINA, another component of the LARTCS, ia a graphite code that can be ueed to interactively create a complex MCNP geometry. Uaera can define many source and tally characteriotica with standard MCNP feature. The time dependent capability of the code is e-ntid wher modeling puloed aourcea, Problems with neutrons, photons, and electrons aa either single particle or coupled particles can be calculated with MCNP, The phycico of neutron and photon transport and interaction is rrmleled in detail using the lateot available crew-bection data, A rich collection of variance reduction featur~can greatly increase the etllciency of a calculation. MCNP u written in FOR TRAN 77 and haa been run m a variety of computer OY* term from scientific workstation to supercomputera. The next production veraicm of MCNP will include features such M continuou-energy electron transport bnd a multitasking option. Arema of ongoing reaesrch of interest to the well logging community include angJe bitwng, adaptive Monte Carle, improved discrete ordinatea capal)ililim, and discrete orrlinatea/Monte Carlo hybrid devebpment. Lom Alarrm haa requested~pprovd by the Department of Enrrgy to create a !ladintion~anuport Computational Facilily Ilndrr their lJw Fncility Progrnm to incr~nm @xternkl intrrnctionn with industry, Ilnivmitiea, and other government orgnnizmtions,

show abstract

Gamma-gamma density measurements: basic response and environmental corrections

Cited by 3 publications

References 4 publications

Calibration models for density borehole logging - construction report

Calibration models for density borehole logging - construction report

Modelling the spatial response of a compensated density tool

MCNP capabilities for nuclear well logging calculations

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