Sec9Neutron Theory
Sec9Neutron Theory
NEUTRON
NEUTRON THEORY
TABLE OF CONTENTS
      TABLE OF
      CONTENTS.................................................................................................i
      INTRODUCTION...........................................................................................................
      .1
                Inelastic
                Collisions..................................................................................................2
                Elastic
                Collisions.....................................................................................................3
      EPITHERMAL NEUTRON
      TOOLS............................................................................13
      THERMAL NEUTRON
      TOOLS...................................................................................14
                Thermal Neutron
                Detector.....................................................................................15
      CAPTURE GAMMA RAY
      TOOLS..............................................................................16
                Pulse Neutron
                Logging...........................................................................................16
      DUAL DETECTOR NEUTRON
      TOOLS.....................................................................17
      NEUTRON TRANSPORT THEORY............................................................................19
     Lithology
     Effects...................................................................................................26
     Formation Fluid
     Effects.........................................................................................28
     Salinity
     Effect........................................................................................................28
     Gas
     Effect..............................................................................................................29
Borehole Effects................................................................................................30
ENVIRONMENTAL CORRECTIONS..............................................................................31
Open Hole..........................................................................................................31
Mudcake Correction..............................................................................32
Standoff Correction................................................................................32
Cased Hole..........................................................................................................36
REFERENCES........................................................................................................................3
9
INTRODUCTION
      The neutron is a fundamental particle found in the nucleus of all atoms except hydrogen,
      which contains only a proton. The neutron has approximately the same mass as the proton
      but carries no electrical charge. These two properties, smallness of size and especially
      electrical neutrality, make it an ideal projectile for penetrating matter. Neutrons pass
      through brick walls and steel plates with the greatest of ease. They can pass through steel
      casing and penetrate rocks. It was logical, therefore, that they should find a place in the
      arsenal of logging tools.
      1. Chemical sources are composed of two elements, which are in intimate contact with
         each other and react together to emit neutrons continuously. The chemical source
         presently used by the industry is americium-beryllium. Chemical sources need to be
         heavily shielded when not in use.
      2. Pulsed sources incorporate an ion accelerator and a target and can be activated by
         electronic means. Presently, pulsed neutron sources are used for pulsed neutron
         logging (TMD) and (PSGT)
4.6 MeV
     Near chemical sources, neutrons may be found with substantially all of their initial energy
     of several MeV; these are called fast neutrons. Neutrons interact with other atoms in
     several ways (which will be discussed later), and they lose energy with each collision and
     move further from the source. After passing through an intermediate stage, the neutron
     energy level drops to only a few eV; these neutrons are called epithermal neutrons.
     After yet more interactions, a neutron will be slowed down to a point where it has the
     same energy as the surrounding matter; this energy level is a direct function of the
     absolute temperature. Such neutrons are called thermal neutrons. They have energies of
     approximately 0.025 eV. It is at this stage that the neutron is ripe for capture. The
     capturing nucleus will usually emit one or more gamma rays. These gamma rays are called
     capture gamma rays.
     The chemical source used by Halliburton is AmBe. The nuclear reaction involves the
     americium producing alpha particles that combine with beryllium in the reaction below:
        241
         95 Am     → 237
                      93 Np + 2 He + γ(60 KeV)
                              4
           4
     9-1. 2 He     + 94 Be →        12
                                     6C    + 01 n + (5.71 MeV )
     5.71 MeV is the reaction energy and is imparted to the carbon atom as recoil energy and
     to the neutron as kinetic energy that sends it into flight. The neutrons have an initial
                                                                   7
     kinetic energy of about 4.6 MeV and a velocity of about 10 m/second. They are
     produced at a rate of 4 x 10 neutrons/second in a 19 curie source.
The two main types of collisions that a neutron may undergo are:
1. Inelastic collisions
2. Elastic collisions
     Inelastic Collisions
     Inelastic collisions can only take place while the neutron is highly energetic. In this type of
     collision, the kinetic energy of the system (neutron and struck nucleus) is not conserved.
     The neutron collides with a nucleus, leaving the nucleus in a higher energy "excited" state.
     The excited nucleus will return almost instantaneously to its ground state by emitting
     gamma rays, which are called "inelastic gamma rays". Figure 1 illustrates this type of
     collision.
                                                                 Target Nucleus
                   Target              Target Nucleus            returns to original state
                   Nucleus             in an exited state
     Fast                                                                          Gamma
    Neutron                                                                        Rays
      A large amount of energy is required to excite a nucleus out of its ground state. This is
      why only neutrons at high energies can undergo inelastic collisions. With each inelastic
      collision, the neutron loses the same amount of energy that the nucleus gains. This implies
      that the neutron can lose a large amount of energy with each inelastic collision. After very
      few inelastic collisions, the neutron is slowed down below the threshold required to excite
      a nucleus and inelastic scattering cannot take place. In general inelastic scattering is only
      important during the first few microseconds of a neutron's life.
      Elastic Collisions
      The second type of collision, and the dominant mechanism by which a neutron loses
      energy, is an elastic collision. Kinetic energy is conserved in these type of collisions. An
      elastic collision is one in which the neutron collides with the nucleus of an atom but does
      not excite the nucleus. The only energy transferred to the nucleus is kinetic (motion)
      energy. This type of collision is illustrated in figure 2.
      During an elastic collision, the neutron will lose a certain amount of energy and the struck
      nucleus will gain that same amount of kinetic energy. The amount of energy that a
      neutron loses in each collision depends on two factors:
      A neutron will lose more energy in a head-on collision with a nucleus than it will lose if the
      neutron just grazes the nucleus. Also, the neutron will lose more energy in a collision with
      a light nucleus than it will in the collision with a heavy nucleus.
Scattered Neutron
                                                                = Scattering Angle
             Incident Neutron
= Recoil Angle
Recoil Nucleus
                                                                                 ε
      The above suggests that a neutron will lose the most energy in a head-on ( = 0) collision
      with a proton, since the proton has about the same mass as a neutron. The maximum
      amount of energy the neutron can lose in an elastic, head-on collision is given by:
                                    4M
      9-2.   ( FE ) max loss =
                                 (1 + M ) 2
      Where ( FE ) max loss is the maximum fractional energy loss and "M" is the mass of the
      struck nucleus in atomic mass units (AMU). The neutron and proton have a mass of 1
      AMU. Using equation (2), Table 2 below shows the maximum fractional energy loss for
      some common downhole elements.
      For most elements, the maximum energy loss is low. A notable exception is the element
      hydrogen (the nucleus contains one proton). A neutron that collides head-on with a
      hydrogen nucleus can lose almost all of its energy in one collision. Not all neutrons will
      lose this maximum amount of energy since most collisions will not be head-on. On the
      average, neutrons will lose about 50% of their energy in each elastic collision with
      hydrogen. The right-hand column of Table 3, shows the average number of collisions
      required to slow a fast neutron (at 2 MeV) to the thermal level.
      Notice the smaller the atom, the fewer collisions that are needed. This, therefore,
      indicates that one of the most important factors affecting neutron theory is the presence of
      hydrogen. Hydrogen is the most effective element in slowing neutrons down, because the
      mass of hydrogen is about the same as the mass of a neutron.
     Table 3 Slowing Down and Capture Cross Sections for 2 MeV Neutrons
      Element                                                 Collisions to 0.025
      Symbol                            Cross Section                 eV
                             Capture              Slowing
             H                 0.30               20.0              18
             Be                0.01               6.1               87
             B                 700.00             3.0               105
             C                 0.00               4.8               115
             N                 1.88               10.0              130
             O                 0.00               4.1               150
             Na                0.51               3.5               215
             Mg                0.40               3.6               227
             Al                0.23               1.5               251
             Si                0.13               1.7               261
             S                 0.53               1.5               297
             Cl                31.60              10.0              329
             K                 2.20               1.5               362
             Ca                0.43               9.5               371
             Fe                2.50               11.0              514
             Cd                2500.00            5.3               1028
             1. The amount of energy loss which a neutron experiences upon making a collision
                with a nucleus of a given mass.
2. The probability that a neutron will collide with this type of nucleus.
                        1
                                                            Clean Sand, Porosity = 15%
                                               Hydrogen
                   10-1
             Slowing
             Down                              Oxygen
             Power -2
                   10
                                               Silicon
                     10-3
                                                 102    103     104    105         6      7
                            .1    1.0     10                                      10     10
                                           Neutron Energy in Electron Volts
     To add to the complexities of the process of slowing down and capture, it should be noted
     that cross sections are also a function of the neutron's kinetic energy before a collision.
     Thus, an analysis of how fast neutrons are scattered in a subsurface formation and
     eventually captured is a complex task. Referring back to Table 3, we have listed the main
     elements found in the logging environment together with their slowing down and thermal
     capture cross sections.
Two elements, hydrogen and chlorine, dominate the behavior of neutron tools.
1. Hydrogen provides the best material for slowing neutrons to a thermal level.
     It should be noted that it is possible for neutrons to be absorbed at higher energy levels
     (e.g. oxygen activation, resonance absorption), but that these absorption processes are
     minor compared to thermal neutron capture. As previously mentioned, once captured the
     new nucleus may very quickly drop to its ground state by emitting capture gamma rays.
      Table 4, below give Lt, Ls and M as a function of porosity for a water-filled sandstone.
      Notice that salt water formations (high chlorine content) have Lt values less than those for
      fresh water. The table gives Ls computed for neutrons degrading in energy from 4.6 MeV
      to 0.025 eV.
      As you can see, the lower the porosity the further the neutrons tend to travel. This means
      that the thermal neutron density at any point in the borehole seen by the detector depends
      on the porosity and how far the detector is from the source. Figure 4 shows a plot of
      thermal neutron density versus the distance from the source, for four different porosities
      (10, 20, 30, 40%).
               Thermal neutron density for point source of Ra-Be neutrons in an infinite formation. These
               curves were calculated using age theory that is know to apply poorly to hydrogenous media.
               Thus they must be used as qualitative quides only.
      Notice that close to the source the neutron density is very high. Also, by comparing the
      10% and 40% porosity curves close to the source, we see that a higher count rate
      indicates a higher porosity. However, as we move away from the source, this
      proportionality fails as we go through the cross over zone. Moving further from the
      source, the count rate versus porosity relationship reverses because neutrons can travel
      further in lower porosity mediums. This means we would expect higher count rate in
      lower porosity if our detector was more than about 30 cm from the source (in reality this
      distance is substantially less than 30 cm).
      Also notice that the greater the distance from the source, the greater the porosity
      resolution. Of course, one disadvantage of this long spaced region is lower count rate.
      Figure 5 illustrates the neutron migration profile "seen" by all present types of neutron-
      porosity logging tools.
     At a point sufficiently removed from the source (i.e. the Long Spaced Region) formations
     with decreased hydrogen content will have relatively more thermal, epithermal and capture
     gamma rays. Since most hydrogen is located in the pore spaces of a formation the neutron
     count rate can be related to a hydrogen index.
                                                                   φ
     This hydrogen index can be considered the porosity; N = H.I*. This is true regardless of
     whether the neutron tool measures thermal neutrons, epithermal neutrons, or capture
     gamma rays. Again, a high count rate indicates a low hydrogen index and hence a low
     porosity. A low count rate indicates a high hydrogen index and hence a high porosity.
     *Notice from equation 9-4, 100% porosity is only indicated for the case of fresh (pure) water. Since our
     reference is fresh water, salt water environments cause problems.
In principle, epithermal neutron tools, due to their insensitive to capture effects, are the most
accurate monitors of formation hydrogen index for any neutron tool employing only one
detector.
The primary drawback of epithermal neutron porosity devices is low count rate at the detectors.
This is due to two effects:
      1. In any region of space there are just not that many epithermal neutrons around (as
         compared to thermal neutrons).
      2. The high energy level of epithermal neutrons make the probability of detection (i.e.
         interaction with helium gas) less likely.
To improve count rate efficiency, most epithermal neutron tools are limited to short source-to-
detector spacing. This, however, results in increased sensitivity to change in borehole diameter
and standoff and reduces the depth of investigation into the formation that, for medium porosity
formation, is approximately equal to the source-to-detector spacing. To improve the situation
somewhat, many epithermal neutron tools are pad mounted "sidewall neutron porosity" devices,
similar in many mechanical respects to density logging tools.
By incorporating source and detector collimation towards the formation into the pad design,
(azimuth collimation), borehole size effects can be minimized, especially in air filled boreholes.
Collimation and limited depth of investigation, however, make sidewall tools more sensitive to
mudcake thickness and severely restrict their utility in cased holes. They are also less effective
in fluid filled uncased wells where hole conditions prevent the pad from maintaining contact
with the formation, or where invasion restricts the utility of the log in identifying gas zones.
Halliburton has developed a dual spaced epithermal neutron tools (DSEN). These tools are not
pad mounted and are used primarily in an air filled boreholes, where count rates are higher.
Thermal neutron tools do not work in an air filled boreholes.
Epithermal neutron detectors are usually constructed as thermal detectors wrapped with a
material that has a very high capture cross section for thermal neutrons. Cadmium wrapped He-
3 gas proportional counters are usually employed. The cadmium effectively absorbs all thermal
neutrons (see Table 3), so that only epithermal neutrons interact with the high pressure
3
2 He gas.
Thermal neutron detectors are, however, more sensitive to lithology and are affected by
borehole and formation salinity. Both thermal and epithermal tools have about the same
sand/lime/dolomite differences.
The thermal parameter Lt is inversely related to the capture cross sections of the specific
elements in the formation and borehole. Elements with high capture cross sections, such as
chlorine in the formation, borehole fluids, and boron in shales, will cause significant decreases
in thermal neutron count rate. Since these decreases are not porosity related, thermal neutron
tool data is often difficult to interpret quantitatively in highly saline or shaly downhole
environments.
Despite these problems, thermal neutron tools are in use today, primarily because of their high
count rate efficiency. Efficiency is especially needed in slim-hole (e.g. cased hole) versions
where only small detectors can be incorporated into the tool.
             1
      9-5. 0 n   + 23He → 31H + 11H + (0.765 MeV)
      The triton (3H) and proton (1H) are the products that ionize the gas. They share the
      reaction energy of 0.765 MeV and as these positive charges move through the gas,
      ionization occurs which causes a stream of electrons to flow to the center high voltage
      anode.(see below)
ANODE
                 3                          CATHODE
                     He GAS
      The streaming electrons will collide with orbital electrons causing secondary ionization.
      This increased electron flow accumulates at the anode and moves on in the form of current
      to cause a pulse outside the counter. The pulse height is proportional to the energy of the
      neutron that initiated the ionization process.
      A thermal detector is essentially 100% efficient for thermal neutrons when He3gas
      pressure is 4 atmosphere or above. For epithermal neutrons, an increase in sensitivity is
      achieved by increasing the gas pressure.
     The energy distribution of formation capture gamma rays is dependent on the elements
     present. As an example, silicon will emit different energy gamma rays following capture
     than will calcium or hydrogen. Since many scintillation type gamma ray detector systems
     can be adjusted so that they are sensitive to gamma rays only in a pre-selected energy
     range, it follows that relative borehole size and lithology sensitivity in capture gamma ray
     tools will vary depending on tool design parameters. In general, hole size and lithology
     effects for capture gamma ray tools are comparable to those for thermal neutron detector
     tools.
      For detection, a time gating method is used with the scintillation type detectors (usually
      NaI or CsI). The advantages in detecting capture gamma rays rather than thermal
      neutrons for Σ are:
             1. Gamma rays can originate from deeper in the formation, i.e. detectors "see" events
                from deeper in the formation;
2. Count rates are higher (multiple gamma rays for each capture);
3. Borehole effect dissipates faster in gamma ray detection versus neutron detection.
      If a neutron tool has a second detector of similar design placed at a different distance from
      the source, the ratio of count rates from the two detectors will retain porosity sensitivity
      while minimizing sensitivity to most other environmental conditions.
      From these readings we find a change in the count rate by a factor of more than 10, due
      entirely to changes in cement thickness. This is the problem with the single detector
      Epithermal tool in casing. The single detector does not have the resolution to determine
      porosity behind casing. With the addition of a second detector, we can now establish a
      ratio. If this ratio held fairly constant with changes in cement thickness, we could then use
      this to define porosity. Looking at the ratios of A and B from Figure 7, we find:
                                        A 20
      Cement Thickness 0", ratio         = = 2.0
                                        B 10
                                        A 59
                                           .
      Cement Thickness 1", ratio         = = 197
                                              .
                                        B 3
                                        A 175
                                           .
      Cement Thickness 2", ratio         =     = 195
                                                  .
                                        B 09 .
      This provides a nearly constant ratio for a constant porosity. In other words, by using a
      ratio of the reading of two detectors, we can eliminate the effects due to the borehole,
      casing and cement. After the ratio is normalized we can use it to derive porosity directly.
      The porosity-ratio transform is usually determined from "fitting" the best curve to actual
      data and has the form:
                                                             x
      9-6.       φ(R) = a o + a 1 R + a 2 R 2 +.... = ∑ a i R i
                                                            i =0
             •    The first group assumes the neutrons range in energy from the source energy down
                  to the epithermal level.
             •    The second group consists of thermal neutrons with the energy degraded
                  epithermal neutrons as a source.
      Physically, both systems can be represented by diffusion equations. These are linear,
      second order, differential equations with no time dependency (we assume no pulse
      generator).
     For the first system (Epithermal group), the diffusion equation can be described as
     consisting of three terms describing the neutron intensity through a unit volume sphere at
     some distant "r" from the source.
        •   The first term is a diffusion term that simply says that the intensity of neutrons will
            change as neutrons simply "move" away from the source and out of the volume.
            This is the so called "diffusion effect" (neutron migration out of the unit volume is
            somewhat offset by neutron migration into the volume).
        •   The second term is a removal effect and gives the probability that the neutrons will
            be removed from the Epithermal group by degrading in energy to the thermal
            group.
        •   The third term is the constant source strength (i.e., AmBe). The Epithermal
            diffusion equation can simply be written as:
     9-7. (Diffusion term)epi + (Removal term)epi+ (Source term)epi = 0
                (no time dependency - from continuous source)
     For the second system, a similar diffusion equation can be constructed for the thermal
     neutron group. As before, there are three terms.
        •   The second term is a removal term that gives the probability that thermal neutrons
            will be removed from the thermal group by absorption by elements within the
            volume.
        •   The third term is a source term whereby, the neutrons removed from the
            epithermal group now become "source" neutrons for the thermal group. The
            thermal diffusion equation can therefore also be simply written as:
      The solution to both diffusion equations can be explicitly solved. For the epithermal
      group we have,
      9-9.               Q  e − r/Ls
              N e (r) =                         Epithermal Solution
                         4 πD s  r
Q = source strength
Ds = diffusion constant
      For a single detector epithermal tool with a source to detector spacing r (see Figure 8),
                                                                               d
      the count rate is given by,
                                           Q  e − rd /Ls
                Count Rate ∝ N e (rd ) =       
      9-10.
                                             π    r
                                           4 D
                                                s   d
      One can see why epithermal tools give the most accurate hydrogen index of all neutron
      type tools. The count rate is shown to be primarily a function of Ls. As already
      discussed, hydrogen dominates the slowing down process of neutrons, and therefore is the
      primary element controlling Ls. From Equation (9-10) we see an increase in hydrogen,
      which causes Ls to decrease, decreases the count rate that implies higher porosity. The
      presence of strong neutron absorbers like chlorine will only effect Ls in the sense that
      hydrogen atoms are replaced by chlorine atoms (thus increasing Ls). Equation (9-10) also
      shows that Epithermal tools are less affected by changes in lithology in the sense that only
      the matrix ability to slow neutrons is a factor, not its ability to absorb them once slowed
      (no Lt effect).
For the thermal group we get a solution to the diffusion equation of the form:
Where:
Q = source strength
      Since the count rate is proportional to N t (r) we see that at a distance "r" from the source,
      the thermal neutron count rate at a detector is a function of both Ls and Lt. Thus, we see
      a dependency not just on the presence of hydrogen but also on the presence of neutron
      absorbers (which control Lt). An increase in the number of such absorbers, like chlorine,
      decreases Lt.
      A compensated thermal neutron tool employs two detectors at a near and far distance rN
      and rF respectively (see Figure 9 below). The two detectors give a ratio of count rates,
      R, from equation (9-11).
Bowspring
Far Detector
rF Near Detector
                        rN
                                                    Source
                                                    Formation
                Formation
      If we now realize that Ls > Lt and both rN and rF are relatively large, equation (12) can
      be approximated by:
                     r           − ( rN − r F ) / L s
      9-13.
              R≈         F
                             e                           Ratio of two thermal detectors count rate
                     r
                         N
      Notice that equation 9-13 has the same form as the epithermal equation 9-10. This
      demonstrates, theoretically, that a compensated thermal neutron ratio should be somewhat
      independent of thermal neutron properties (salinity, etc.), because the dependency on Lt
      vanishes. Unfortunately equation 9-13 only holds true for "r" values out of the physical
      range of practical logging tool limits (the greater "r" the lower the count rate and the more
      statistical the measurement). Nevertheless the approximation equation 9-13 still
      demonstrates that a ratio method has a weaker dependency on Lt. Notice from equation
      9-13 that as hydrogen content increases, Ls decreases and the ratio increases as it should
      for higher porosity’s (φ α R).
      Theoretically and realistically speaking, the intensity of capture gamma radiation resulting
      from the absorption of thermal neutrons can be used to determine the thermal neutron
      density N t (r) and therefore porosity or Σ. This is possible because, obviously, the count
      rate for the capture gamma rays is proportional to N t (r). That is, as we have already
      stressed, the more thermal neutrons in a volume, the more that will be captured, and the
      greater the number of emitted gamma rays.
     Lithology Effects
     Most matrix elements have different inelastic, elastic and thermal neutron capture
     properties. Although the magnitudes of these effects are usually small relative to the
     hydrogen effect, they do cause slight changes in the neutron slowing down length (Ls) and
     the thermal diffusion length (Lt). For example, the neutron slowing down length (the
     dominant factor affecting porosity) is always slightly larger in a sandstone (quartz)
     formation than in a limestone (calcite) formation of the same porosity. Table (5) shows
     the slowing down lengths for calcite, dolomite and sandstone. The slowing down lengths
     correspond to neutron energy degraded from 4.6 MeV to 1.46 eV.
      If a neutron tool moves from a limestone to a similar sandstone (same porosity) and the
      log analyst is not aware of the change in lithology, he would incorrectly attribute the
      increase in count rate to a decrease in porosity. By contrast, in going from limestone to a
      similar dolomite a lower count rate would result because of the shorter Ls, thus indicating
      a higher porosity. Lithology correction graphs like the one below for the DSNT (Dual
      Spaced Neutron Tool) can be used to correct porosity for lithology effects. It should be
      noted that graphs such as these assume certain values for sigma matrix (thermal neutron
      capture cross section) that may not be correct.
     Lithology induced fractional errors in the indicated porosity will be larger for low porosity
     formations. Here, the contribution of the matrix is greater.
     Epithermal tools' lithology effect is smaller than that of thermal tools, because that small
     portion of the matrix effect caused by neutron absorption (i.e., Lt) is eliminated.
     Therefore, Epithermal type tools give better porosity estimates that are less sensitive to
     lithology changes, especially at low formation porosities. This relative insensitivity to
     lithology changes is also a disadvantage of the Epithermal type tools for use in lithology
     cross-plot applications.
     Salinity Effect
     As stated earlier, chlorine is an excellent thermal neutron absorber compared to other
     common downhole elements. In formations containing chlorine (i.e. salt water), the
     thermal neutrons are quickly captured. This premature capturing reduces the number of
     collisions a thermal neutron will have before being captured, and reduces the thermal
     diffusion length, Lt. The net result is, at some fixed distance from the source, fewer
     thermal neutrons will be present in saline formations compared to fresh formations of the
     same porosity.
     Since the standard tool reference for neutron tools assume fresh water is in the formation,
     environmental correction charts must be used when saline water is present.
     Capture gamma rays' intensity cannot be easily predicted in relation to formation water
     salinity. Although the concentration of thermal neutrons is reduced in saline formations,
     the resulting capture gamma ray intensity can even increase in some instances. This
     offsetting effect occurs since chlorine emits more gamma rays following neutron capture
     than most other downhole elements.
      Gas Effect
      Replacement of liquid by gas in the pore space of a rock lowers the hydrogen density of
      the pore fluid. As a result the neutron tool, that is calibrated for liquid-filled porosity,
      indicates abnormally low porosity (i.e. it sees gas as water occupying a smaller
      volume).
      In the case of formations with considerable gas saturation’s, another effect is present.
      This is known as the "excavation effect". Consider a formation with 10% porosity
      completely saturated with gas having a hydrogen index of 0.1. This formation will contain
      the same amount of hydrogen as a fresh water filled formation with a 1% porosity. The
      count rate observed in the gas filled formation will be greater.
      The 1% porosity fluid filled formation has 99% rock matrix, while the 10% porosity gas
      filled formation only has 90% rock matrix. In the case of the gas filled formation, 9% less
      rock matrix is present to absorb, scatter and attenuate neutrons and gamma rays. The shift
      in the count rate due to the excavation effect is larger for higher porosity zones with
      intermediate gas saturation’s.
      Neutron tools respond only to the total amount of hydrogen in a formation. Since shales
      contain hydrogen that is not part of the porosity, any porosity estimates in shaly zones will
      be too optimistic. This is also true of gypsum since it contains bound water of
      crystallization.
      In addition to bound water effects, there are an additional lowering of thermal neutron and
      capture gamma ray intensities in shaly zones due to their unusually large capture cross
      sections. Most shales contain trace concentrations of elements with extremely high
      thermal neutron capture cross sections. The most important of these is boron. Boron has
      a capture cross section almost 25 times larger than chlorine. Even small concentrations of
      boron (typically 100 parts per million in shales) can cause a large increase in the overall
      formation capture cross section.
      Rare earth minerals present in trace amounts can cause similar effects: porosities may
      appear optimistic due to abnormally low count rates. Of course, the magnitude of the
      effect depends upon the specific minerals present and the type of detectors used.
     The capture gamma ray intensity, which is only slightly sensitive to salinity due to the
     offsetting effects described earlier, is very sensitive to shaliness. Boron, unlike most other
     formation elements, does not emit high energy gamma rays following thermal neutron
     capture. Instead, boron emits non-penetrating alpha particles (helium nuclei) and low
     energy gamma rays that are usually unable to reach the detector. This reduces the count
     rate in a gamma ray detector and results in an optimistic porosity calculation.
     Borehole Effects
            LIQUID FILLED BOREHOLES
     Changes in the borehole environments also produces changes in neutron and capture
     gamma ray count rates. Since neutron tools are calibrated to a standard conditions, any
     departure from these standards must be quantified and corrected. In the open hole the
     perturbation effects include those due to: the presence of mud and mud cake, the size of
     the hole, the eccentricity (standoff) of the tool, the presence of chlorine, the pressure of
     weighting materials and borehole temperature. In the cased hole the neutron and capture
     gamma ray distribution is also effected by the presence of the iron casing and surrounding
     cement.
     The "Environmental Correction" section will elaborate more on these effects and define
     the type of correction needed.
     The relationships between hole size and observed count rate are opposite for air and liquid
     filled holes. In an air filled borehole, the observed count rate increases with increasing
     borehole diameter. The net result of all known borehole phenomena is a very significant
     reduction in the effectiveness of most neutron tools in air filled holes. As previously
     mentioned epithermal tools are the only recommended neutron porosity devices for
     air filled holes.
ENVIRONMENTAL CORRECTIONS
      Open Hole
      The basic neutron porosity response represents "true" formation porosity only if the
      borehole and formation conditions are "standard". When non-standard conditions are
      encountered, corrections must be applied to the porosity values. We shall discuss the
      correction applied to a dual spaced thermal neutron tool. Although the corrections may
      be numerous, they are much smaller in magnitude than corrections for a single-detector
      neutron porosity tool and, in many cases, tend to cancel algebraically (see Figure 11). The
      physical rational for the direction of each correction (positive or negative) will be
      explained. Although performed on the thermal neutron tool, the same rationale and
      direction of each environmental correction is also correct for epithermal type tools; only
      the magnitudes of the corrections are different.
      Since the porosity is a function of the ratio of the near to far detector count rate [φ (R) = φ
      (N/F)] , the far detector count rate essentially controls porosity estimates. This is due to
      the fact that it changes much more dramatically than the near, i.e. an increase in porosity is
      essentially due to the far detector count rate decreasing significantly while the near
      decreases less dramatically (fractionally speaking). For the DSNT-A, a change in porosity
      from 10% to 40% shows the near count rate decreases by 43%, while the far decreases by
      81%. As with all present neutron type tools, both thermal detectors are placed at a
      sufficient distance to give an inverse relationship between count rate and porosity.
      The magnitude of the borehole effect increases as the apparent porosity increases. As the
      apparent formation porosity increases, a greater fraction of neutrons from the source are
      thermalized and captured within the formation and, do not reach the detectors. The count
      rate from the borehole, however, remains relatively constant. As φ (R) increases, the
      fraction of total tool response from the borehole increases. This means that at high
      apparent formation porosities, the borehole tends to dominate the tool response; thus the
      borehole correction becomes greater as φ (R) increases.
            MUDCAKE CORRECTION
     The effect of the mudcake on the recorded porosity depends on a complicated relationship
     between mud, mudcake and if the log porosity is auto caliper corrected. An increase in
     mudcake thickness will increase the amount of hydrogen near the tool. This reduces the
     count rate and increases the apparent porosity. Mud cake effects usually require a
     negative correction.
     •   First, the added NaCl increases the thermal neutron capture cross section of a fluid.
         This tends to reduce neutron count rates.
     With formation salinity, the increased capture cross section of the formation water is the
     dominant effect. As the salinity of the formation fluid increases, the count rate decreases
     ,and the apparent porosity is too high. A negative correction is usually required.
     With the borehole, the decrease in hydrogen index of the borehole fluid is the dominant
     effect. This is due to the fact that the borehole's largest influence is with neutrons as they
     leave the source. These high energy neutrons are not affected by the capture properties
     of the borehole fluid. Overall, an increase in borehole fluid salinity will increase count
     rates and yield a recorded porosity that is too low. A positive correction is required.
     It should also be mentioned that the type of mud must also be considered. Barite mud,
     due to the higher density of the solid material, will have a higher hydrogen index than
     natural mud of the same weight. As an example, 16 lb/gal barite mud has approximately
     the same hydrogen index as 12 lb/gal natural mud. The correction should be the same for
     both.
             STANDOFF CORRECTION
      An increase in tool standoff from the formation places more hydrogen between the tool
      and formation. This tends to reduce count rates and increase the apparent porosity. A
      negative correction is required.
      The magnitude of the standoff correction increases with standoff distance until the tool is
      centralized within the borehole and then begins to decrease. This effect can be illustrated
      as follows. Recall that the neutron tool is not collimated. Assume that we have a 3.5"
      O.D. tool in a 5.0" borehole. A 0.5" standoff will produce a negative correction. Yet as
      the standoff is increased to 1.5", the tool is actually against the opposite side of the
      borehole wall and, by definition, the correction must be zero. All standoff corrections
      must, therefore, be a function of borehole diameter as well as standoff distance in order to
      by physically meaningful.
             BOREHOLE TEMPERATURE CORRECTION
      As the temperature of a fluid increases, the density of that fluid (and its hydrogen index)
      will decrease. An increase in pressure increases the hydrogen index of a fluid. Higher
      temperatures will increase the count rate and reduce apparent porosity. Higher pressures
      have the opposite effect but to a much smaller extent. The temperature correction
      includes a pressure correction that assumes an increase in pressure with an increase in
      temperature. A positive correction is the result. If the pressure and temperature
      corrections are performed separately, the pressure correction would be negative, while the
      temperature correction would be positive. Figure 11 and 12 show the corrections that are
      applied to the neutron response in the open hole.
Figure 11
Figure 12
     Cased Hole
     In addition to the borehole diameter (before casing), borehole salinity, formation salinity,
     mud weight and borehole temperature effects, additional corrections are required in the
     cased hole due to the presence of steel casing and cement.
            CASING THICKNESS CORRECTION
     Iron is a good thermal neutron scatterer and absorber. An increase in the casing thickness
     above the standard increases the amount of iron between the formation and the tool. The
     iron tends to reduce the neutron intensity within the borehole. This reduces count rate and
     makes the apparent porosity too high. The correction applied is therefore negative. The
     correction is positive for casing thickness less than the standard.
      Choosing the wrong lithology can give a false gas effect (i.e., choosing limestone when the
      actual matrix is sandstone). Figure 14 shows a neutron - density log using a limestone
      matrix. Notice the false gas effect through the sand section.
REFERENCES
      1. Smith, Harry D., Nuclear Logging Lectures, (1981)
      2. Bateman, Richard M., Open-Hole Log Analysis and Formation Evaluation, IHRDC,
         Boston, 1985
      3. Weidner, Richard T., Robert L. Sells, Elementary Modern Physics, Allyn and Bacon,
         Inc., Boston, 1972
      4. Dewan, John T., Essentials of Modern Open-Hole Log Interpretation, Penn Well
         Publishing Company, Tulsa Oklahoma, 1983
      6. Sears, Francis W., Mark W. Zemansky and Hugh D. Young, University Physics,
         Addison-Wesley Publishing Company, Reading, Mass., 1977
      7. Smith, Mike P., "Calibration, Checking and Physical Corrections for a new Dual-
         Spaced Neutron Porosity Tool", SPWLA Symposium, June, 1986