NEUTRON LOGGING OF DRILL HOLES: THE NEUTRON‐NEUTRON METHOD

Geophysics ◽  
1951 ◽  
Vol 16 (4) ◽  
pp. 626-658 ◽  
Author(s):  
C. W. Tittle ◽  
Henry Faul ◽  
Clark Goodman

Experiments were performed to determine the distribution of thermal neutrons and of indium resonance neutrons in continuous hydrogenous media and in pipes passing through hydrogenous media. Included in the study were water, brine, mixtures of sand and water, and mixtures of sand and brine. Experiments in a continuous typical barite drilling mud showed that the neutron distributions were essentially the same as in water. Also, from the point of view of these experiments, oil and fresh water are nearly identical. These experiments show that well fluid (and, by inference, cement) imposes serious limitations on the sensitivity and accuracy of the neutron‐neutron logging method. The indium resonance neutron response (or, in general, the intensity of epithermal neutrons) is a more reliable indicator of hydrogen content of the formation than is the thermal neutron response. The neutron‐neutron method of chlorine determination was found to be not sensitive enough to be useful with brines of the concentrations ordinarily found in reservoirs.

Geophysics ◽  
1951 ◽  
Vol 16 (2) ◽  
pp. 260-276 ◽  
Author(s):  
Henry Faul ◽  
C. W. Tittle

The intensity distribution of secondary gamma radiation resulting from neutron capture has been measured in simulated drill holes, of various types such as cased and uncased, empty and water‐filled. The intensity of neutron‐capture gamma rays depends on the hydrogen content of the rock. In a six‐inch well, it increases with hydrogen content at points within about 16 inches of the neutron source and decreases at more distant points. The absolute gamma intensity is greatly reduced when non‐hydrogenous gamma‐ray or neutron absorbers, e.g., lead or boron are introduced between logging probe and formation. The slope of logarithmic gamma ray intensity vs. distance remains virtually constant. It changes with the hydrogen content of the formation and offers a means of quantitatively estimating porosity behind casing despite extraneous absorption. The slope can be measured automatically in the well by two gamma detectors placed in a probe at fixed distances from a neutron source. Hydrogenous material between probe and rock increases the slope. Two or three inches of drilling mud seriously impair the sensitivity. Gamma radiation scattered by the walls of drill holes necessitates proper shielding for detectors used in (n, γ) logging with a radium‐beryllium source. A shielded detector is predominantly sensitive to the hard neutron‐capture gamma rays and tends to discriminate against the softer scattered radiation. The scattered intensity decreases with increasing bulk density of the formation. Under favorable conditions, continuous logs of formation density as a function of depth can be obtained.


1972 ◽  
Vol 3 (3) ◽  
pp. 33
Author(s):  
B.M. Haines ◽  
D.W. Emerson

In order that the whole suite of geophysical logging methods may be employed, it is necessary that the borehole contain drilling mud. Usually in shallow water bores this mud consists simply of a clay component and make-up water, although during drilling it also contains particles and fluids derived from the formations penetrated. The major purposes of the mud, from the driller's point of view, are to lubricate and cool the bit, to prevent caving especially in unconsolidated sediments and to carry bit cuttings to the surface. While the mud composition may be relatively simple, the physical, electrical and chemical system comprising the mud column and formation is rather complex. Mud filtrate, a fluid extract of the mud, is expressed and enters the formations under the influence of differential hydrostatic pressure; consequently, a mud cake is formed on the borehole walls; and the filtrate itself provides electrochemical contrasts with the formation waters. The system is further complicated by the frequently unsystematic approach to the specification and control of drilling mud, and the general lack of understanding of the system as a dynamic entity. The volume of influence of all well logging methods therefore includes drilling mud, mud cake, invaded and uninvaded formation, these latter being wholly or partially saturated by filtrate and formation water respectively. For purposes of quantitative log interpretation, especially in regard to electrical logs, it is a necessary prerequisite that the electrical properties of the mud and its derivatives be either measured directly, or derived through established relationships with readily measured properties. A limited laboratory experimental study has indicated the relationships between the electrical and physical properties of the mud system and the influence of solids content. Field testing of these relationships showed that they are extensively modified in both form and magnitude by formation particles and waters acquired during drilling. It is apparent that relationships are strongly dependent on several factors, and should be evaluated separately for individual borehole/mud/formation systems.


Universe ◽  
2018 ◽  
Vol 4 (12) ◽  
pp. 134 ◽  
Author(s):  
Georgios Tsiledakis ◽  
Alain Delbart ◽  
Daniel Desforge ◽  
Ioanis Giomataris ◽  
Thomas Papaevangelou ◽  
...  

Due to the so-called 3He shortage crisis, many detection techniques for thermal neutrons are currently based on alternative converters. There are several possible ways of increasing the detection efficiency for thermal neutrons using the solid neutron-to-charge converters 10B or 10B4C. Here, we present an investigation of the Micromegas technology. The micro-pattern gaseous detector Micromegas was developed in the past years at Saclay and is now used in a wide variety of neutron experiments due to its combination of high accuracy, high rate capability, excellent timing properties, and robustness. A large high-efficiency Micromegas-based neutron detector is proposed for thermal neutron detection, containing several layers of 10B4C coatings that are mounted inside the gas volume. The principle and the fabrication of a single detector unit prototype with overall dimension of ~15 × 15 cm2 and its possibility to modify the number of 10B4C neutron converter layers are described. We also report results from measurements that are verified by simulations, demonstrating that typically five 10B4C layers of 1–2 μm thickness would lead to a detection efficiency of 20% for thermal neutrons and a spatial resolution of sub-mm. The high potential of this novel technique is given by the design being easily adapted to large sizes by constructing a mosaic of several such detector units, resulting in a large area coverage and high detection efficiencies. An alternative way of achieving this is to use a multi-layered Micromegas that is equipped with two-side 10B4C-coated gas electron multiplier (GEM)-type meshes, resulting in a robust and large surface detector. Another innovative and very promising concept for cost-effective, high-efficiency, large-scale neutron detectors is by stacking 10B4C-coated microbulk Micromegas. A prototype was designed and built, and the tests so far look very encouraging.


2013 ◽  
Vol 2013 ◽  
pp. 1-6 ◽  
Author(s):  
Yun-Shao Cho ◽  
Chia-Hsun Hsu ◽  
Shui-Yang Lien ◽  
Dong-Sing Wuu ◽  
In-Cha Hsieh

Influences of hydrogen content in intrinsic hydrogenated amorphous silicon (i-a-Si:H) on performances of heterojunction (HJ) solar cells are investigated. The simulation result shows that in the range of 0–18% of the i-layer hydrogen content, solar cells with higher i-layer hydrogen content can have higher degree of dangling bond passivation on single crystalline silicon (c-Si) surface. In addition, the experimental result shows that HJ solar cells with a low hydrogen content have a poor a-Si:H/c-Si interface. The deteriorate interface is assumed to be attributed to (i) voids created by insufficiently passivated c-Si surface dangling bonds, (ii) voids formed by SiH2clusters, and (iii) Si particles caused by gas phase particle formation in silane plasma. The proposed assumption is well supported and explained from the plasma point of view using optical emission spectroscopy.


CrystEngComm ◽  
2020 ◽  
Vol 22 (19) ◽  
pp. 3269-3273
Author(s):  
Shuangliang Cheng ◽  
Rachel E. Hunneke ◽  
Mengkun Tian ◽  
Eric Lukosi ◽  
Mariya Zhuravleva ◽  
...  

We developed novel LiCl–CeCl3 eutectic scintillators that are capable of detecting thermal neutrons.


2002 ◽  
Vol 74 (0) ◽  
pp. s1710-s1712 ◽  
Author(s):  
Y.N. Choi ◽  
H.S. Oh ◽  
V.T. Em ◽  
V.A. Somenkov ◽  
C.-H. Lee ◽  
...  

1970 ◽  
Vol 10 (04) ◽  
pp. 365-379 ◽  
Author(s):  
J.S. Wahl ◽  
W.B. Nelligan ◽  
A.H. Frentrop ◽  
C.W. Johnstone ◽  
R.J. Schwartz

Abstract Thermal Neutron Decay Time (TDT) logging tools in 3-3/8 and 1-11/16-in. diameters have been developed for detection and evaluation of water saturation in cased holes. These tools utilize a system of movable and expandable detection time-gates which are automatically adjusted as the log is being run. The two principal detection gates are positioned in time after the neutron burst according to an optimization criterion. An additional gate, delayed until most of the decay has taken place, permits correction for background. This place, permits correction for background. This Scale Factor gating method provides, in each bed, a thermal-decay-time measurement of maximum statistical precision consistent with removal of borehole effects present in the early part of the decay period Increased reliability is afforded by use of digital techniques. Thermal neutron decay time tools employ capture-gamma-ray detection. This choice was based on an extensive series of experiments made to compare gamma-ray detection and direct detection of thermal neutrons. Measurements of thermal neutron decay time constant are affected by local changes in neutron density in the vicinity of the sonde, caused by flow of neutrons by diffusion from one medium to another. The measured decay time constant (T meas) of neutron density at any point may differ, therefore, from the intrinsic decay time constant (T int) produced by absorption alone. The basic physics of neutron diffusion and absorption is reviewed. When the borehole and the formation have different decay time constants and diffusion coefficients, diffusion couples the two regions. Consideration of such effects sheds light on the conditions required for reduction of borehole effects on measured values of the decay time constant. The choice of source-detector spacing is affected. and, for accurate quantitative interpretation, departure curves are required. Departure curves are presented showing the effects of varying cement thickness, casing diameter. and casing fluids Illustrative log examples are shown. Introduction The Thermal Neutron Decay Time (TDT) log provides a determination of the time constant for provides a determination of the time constant for the decay of thermal neutrons in the formation. Hence, it reflects primarily the neutron absorptive properties of the formation. These properties are properties of the formation. These properties are useful in formation evaluation. The most important area of application is in logging cased hole. Because chlorine is by far the strongest thermal neutron absorber of the common earth elements, the TDT log responds largely to the amount of NaCl present in the formation water. As a result, this present in the formation water. As a result, this log resembles the usual open-hole resistivity logs and is easily correlatable with them. When information on lithology and porosity is known or is provided by open-hole logs, a log of neutron provided by open-hole logs, a log of neutron absorption properties permits the solution of a wide variety of problems: saturation determination, oil-water contact location, detection of gas behind casing, etc. Measurements of the thermal neutron decay time constant are made by first irradiating the formation with a pulse of high-energy neutrons from a neutron generator in the sonde, and then, a short time after the neutron source is turned off, determining the rate at which the thermal neutron population decreases. After each neutron burst, the high-energy neutrons are quickly slowed down to thermal velocities by successive collisions with the nuclei of elements in the formation and borehole. The relative number of thermal neutrons remaining in the formation is measured during detection intervals which follow each burst. Between each burst and the beginning of the first detection interval is a delay time which permits the originally fast neutrons to reach thermal permits the originally fast neutrons to reach thermal energy and allows "early" borehole effects to subside. SPEJ p. 365


2021 ◽  
Vol 253 ◽  
pp. 04011
Author(s):  
Małgorzata Wróblewska ◽  
David Blanchet ◽  
Abdallah Lyoussi ◽  
Patrick Blaise ◽  
Zuzanna Marcinkowska ◽  
...  

This paper presents an advanced optimization analysis of the newly developed transmission measurement method conducted in the MARIA MTR reactor for thermal neutrons absorbers estimation in irradiated beryllium elements. Several neutron sources in combination with various thermal neutron detectors are investigated, along with the optimization of the moderating polyethylene layer to improve the signal to background ratio. It was concluded that the use of 239PuBe or 241AmB neutron source with polyethylene of 0.95 g/cm3 density and ∼4.5 cm thickness, as well as either 235U lined fission chamber or BF3 detectors are meeting the requirements for the use in the experiment.


2021 ◽  
Author(s):  
Chao Wang ◽  
Zhefu Li ◽  
Mengge Dong ◽  
Lu Zhang ◽  
Jianxing Liu ◽  
...  

<p>Although the various excellent properties and preparation methods of TiB<sub>2</sub>-based composites have been extensively studied, their neutron shielding properties have not received as much attention. In this article, the neutron shielding performance of the previously prepared TiB<sub>2</sub>-Al composite will be studied. The photo neutron source device was used to carry out neutron irradiation tests on test samples with a thickness of 10 mm. The average thermal neutron shielding rate of TiB<sub>2</sub>-based boron-containing composites is 17.55%, and the shielding rate increases with the increase of BN content. The macroscopic cross-section of thermal neutrons of the composites generally shows a stable trend, and when the BN content is 10%, the thermal neutrons macroscopic cross section reaches the maximum value of 7.58cm<sup>-1</sup>. With the increase of the BN content, the thermal neutron fluence rate shows a gradually decreasing trend.</p>


Author(s):  
Moustafa Oraby

AbstractThe thermal neutron porosity is routinely acquired in almost every well. When combined with the density, gamma ray and resistivity logs, the basic petrophysical parameters of a reservoir are evaluated. The design of the thermal neutron tool is simple, but its interpretation is complex and affected by the formation constituents. The most challenging situation occurs when the formation contains elements with high absorption probability of the thermal neutrons. The existence of such elements changes the neutron transport parameters and results in a false increase in the measured porosity. The problem is reported by many users throughout the years. In 1993, higher thermal neutron porosity is reported due to the existence of an iron-rich mineral, Siderite, in the Nazzazat and Baharia formations in Egypt. Siderite and all iron-rich minerals have high thermal neutrons absorption probability. Recently, in 2018, high thermal neutron porosity in Unayzah field in Saudi Arabia is also reported due to the existence of few parts per million of gadolinium. Gadolinium is a rare element that has high probability of thermal neutron absorption. Currently, none of the existing commercial petrophysics software(s) have modules to correct the thermal neutron porosity for such effects. This represents a challenge to the petrophysicists to properly calculate the actual reservoir porosity. In this paper, the effects of the rare elements and other minerals with high thermal neutron absorption probability on the thermal neutron porosity are discussed, and a correction methodology is developed and tested. The methodology is based on integrating the tool design and the physics of the neutron transport to perform the correction. The details of the correction steps and the correction algorithm are included, tested and applied in two fields.


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