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Study of the Influence of Casing and Liquid Inside Oil Wells on the Response of Neutron Logging Tools


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Abstract


The influence of the casing and liquid inside the borehole in  neutron porosity tool response is analyzed. For this, MCNPX simulation of neutron tool inside of a slim borehole was performed. The results showed that the presence of PVC casing and liquid inside the borehole reduces the tool response in about 73% for low porosities, and 90% for high porosities.
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Keywords


Nuclear Well Logging; Neutron Porosity; MCNPX; Casing Influence; He-3 Detector

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References


Duijvestijn M., Hogenbirk A., Koning, A. (2002), Sensitivity to Nuclear Data in Oil-Well Logging Applications, Journal of Nuclear Science and Technology, Supplement 2, 1384-1387.

Gardner R.P., Sood A. (2010), On the Future of Monte Carlo Simulation for Nuclear Logs, Applied Radiation and Isotopes, 68, 932-935.

Nordlung A., Avdic S., Dahl B., Kaiser, N. (2001), Transmission measurement of porosity with a neutron generator in geophysics application, Nuclear Instruments and Methods in Physics Research A, 462, 451-456.

Parvaresh P., Sohrabpour M. (2004), Design and testing of a neutron porosity probe using MCNP code, Journal of Radioanalytical and Nuclear Chemistry, 260, 335-337.

Hendricks J. S., McKinney G. W., Fensin M. L. et al (2008), MCNPXTM User's Manual, version 2.6.0. LA-CP-07-1473, Los Alamos National Laboratory.

Abhold M. E., Baker M. C. (2002), MCNP-REN: A Monte Carlo Tool for Neutron Detector Design, Nuclear Instruments and Methods In Physics Research Section A, 45, n. 11, issue 3, 576-587.

Angarou K., Iacoste V., Muller H., Fernández F. (2007), Set-up of Passive Bonner Sphere System for Neutron Spectrometry at Mixed Fields with Predominant Photon Component Based on Activation Detector, Radiation Protection Dosimetry, 126, issue: 1-4, 337-341.

Bolewski Jr. A., Ciechanowwki M., Dydejczyk A., Kreft, A. (2008), On the optimization of the isotopic neutron source method for measuring the thermal neutron absorption cross section: Advantages and disadvantages of BF3 and 3He counters, Applied Radiation and Isotopes, 66, issue: 4, 457-462.

Hendriks P. H. G. M., Maucec M. De Meijer, R. J. (2002), MCNP Modelling of Scintillation-detector Gamma-Ray Spectra from Natural Radionuclides, Applied Radiation and Isotopes, 57, n. 3, issue: 9, 449-457.

Wang Z., Kahn B., Valentine J. D. (2001), Efficiency Calculation and Coincidence Summing Correction of a Germanium Detector by Monte Carlo Simulation, IEEE - Nuclear Science Symposium Conference Record, 2, Issue: 4-10, 1037-1041.

Van Riper K. A. (2006), MORITZ Geometry Toll User's Manual: An Interactive Geometry Editor/Viewer for MCNP & MCNPX, White Rock Science, USA.

Knoll G. F. (1999), Radiation Detection and Measurement. 3rd ed., John Wiley and Sons, University of Michigan, USA.


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