The Effect of the E1 Strength Function on Neutron Capture Cross Sections Berkley J.T. Starks Brigham Young University-Idaho 009 March 18 1. Introduction The myriad of phenomena that are observed throughout the universe stem from the interactions of 4 main forces. These forces in order of weakest to strongest are gravity, the weak nuclear force, the electromagnetic force, and the strong nuclear force. The electromagnetic force and the strong nuclear force are the primary factors as to the physical makeup of matter throughout the universe. The interplay of these forces is made clearly manifest within the atomic nucleus. Key to the study of nuclear physics is the nuclear cross section. Nuclear cross sections are a measure of the probability of certain reaction occurring. Dr. Krane defines the differential cross section, dσ/dω, as the probability that an incident particle, dσ, is scattered into the unit solid angle, dω. The probability of dσ being scattered into dω is the ration of the scattered current through dω to the incident current. The total cross section, σ, is the total probability of scattering in any direction. 1A. Nucleosynthesis Nucleosynthesis attempts to interpret the measured abundances of the nuclear species in terms of their nuclear properties and a set of environments in which nuclei can be synthesized by nuclear reactions. (Clayton, 69). Nucleosynthesis depends on networks of nuclear reactions/processes in order to produce all heavy elements. Key to these reaction networks is the cross section. It is theorized that most of the lighter elements (Z 6) were synthesized during the Big Bang. The rest of the elements with nuclear charge Z 6 are in fact the ashes of nuclear burning during stellar evolution. (Clayton, 71). The basic hypothesis of these studies as stated by Chandrasekhar is that: Apart from secondary effects of minor importance, the transmutation of of elements is the entire cause of the presence of all elements in the stars; they are all being synthesized continually in the stars which are assumed to have started as pure masses of hydrogen; (Chandrasekhar, 469) From this we can see the importance of nucleosynthesis studies in astrophysics. By using particle fluences and thermodynamic conditions in stars, we are able to understand the observed abundances of stable isotopes.
1B. Nuclear Cross Sections Nuclear cross sections determine the probability of of a process occurring. A cross section is highly dependent on the energy of the incident particle(s). As was discussed above, the differential cross section, dσ/dω, is the probability that an incident particle, dσ, is scattered into the unit solid angle, dω. From nucleosynthesis we can see the importance of cross sections in the creation of elements through the reaction networks. While we measure all cross sections that we are able to do, there are many unstable isotopes that it is impossible to test on. The problem lies in that these isotopes are produced in reaction networks, and will influence and interact with the other particles involved in the reaction. Because we are not able to test upon these isotopes, theory must provide cross sections for them if we are to fully understand the reaction networks. In measuring these cross sections there are several different reaction networks depending on the type of incident energy. One of the most critical is neutron capture cross sections. Neutron capture cross sections, n,, have several important ingredients. Most important at low energies is the photon transmission coefficient. Making up the photon transmission coefficient is the gamma ray strength function, f XL, the energy dependent width of the giant dipole resonance, GDR, T f, and the E1 strength function. In order to be able to increase the accuracy of theory, we must be able to reproduce measured cross sections on stable isotopes. The issue comes from that there are several ways to model the E1 strength function. Each of these models reproduces experimental cross sections in localized regions of the periodic table, but none are able to globally reproduce experimental cross sections. What we will be doing is modeling the E1 strength function using several different schemes and attempting to see if one model as a better global fit to the others. When calculating these models there are two ways to normalize the photon transmission coefficient, specifically to the model used for the E1 strength function. This can be normalized either to the average radiation widths,, at the neutron binding energy, Bn, or the E1 strength can be normalized to the Maxwellian averaged cross section (MACS). What we are trying to do is see what effect the E1 strength function has upon the cross section, and if by finding the appropriate f E1 we are endeavoring to be able to reproduce the experimental n, cross sections and be able to replicate both B n and 30 kev MACS. 1C. Some Basic Notation The following section will give a brief overview of the notation throughout this document. The notation used is the same as found in reference 4. Z - Proton number of the nucleus N - Neutron number of the nucleus A - mass of the nucleus in atomic mass units (generally A=Z+N)
J - angular momentum π - parity lower case letters - n, p, α, or γ particles capital letters nucleus (not n, p, α, or γ particles) - A further and more in-depth explanation of the notation will explained within chapter of this thesis under the section entitled The Hauser-Feshbach Statistical Model.
. Review of Theory A. Direct and Compound Reactions In a nuclear reaction there are two main types of processes that occur. These reactions types are called direct processes and compound processes. Direct reactions involve only very few nucleons...with the remaining nucleons of the target serving as passive spectators (Krane p. 379). These reactions only remove or insert a single nucleon from the target nucleus and are used to help explore and analyze the spectroscopic states in nuclei. Compound reactions happen when the incoming and target nuclei briefly merge and completely share the incident energy before the outgoing nucleons are ejected. One of the most important assumptions of the compound-nucleus model is that the relative probability for decay into any specific set of final products is independent of the means of formation of the compound nucleus (Krane pp. 416-417). An example of a compound process is the formation and then decay of 64Zn. 64Zn can be formed by either p + 63Cu or α + 60Ni. After 64Zn* is formed it can then decay into 63Zn + n, 6Cu + n + p, or 6Zn + n. The decay of 64Zn is completely independent of the way that it is formed. Whether it is through a proton capture, or and alpha capture, the formation does not affect the decay of the compound nucleus. As can be seen from the graphs below, the shape of the cross sections are relatively the same with only slight perturbations. The two experimentally observable differences between direct and compound reactions are (1) Direct processes occur very rapidly, in a time of the order of 10 - s, while compound-nuclear processes typically take much longer, perhaps 10-16 to 10-18 s...() The angular distributions of the outgoing particles in direct reactions tend to be more sharply peaked than in the case of compound-nuclear reactions (Krane pp. 419-40). This last point is due to the fact the since the nucleus remembers how it was made, the momentum of the incident particle is going to transfer its momentum in the same incident direction upon the target nucleons. One other difference between direct and compound reactions is summarized by Dr. Krane in that incident 1-MeV neutrons have a wavelength of ~ 4 fm. Because of this a 1-MeV neutron is most likely
to interact through compound nuclear reactions. Direct reactions involve higher energies (~0-MeV) have a de Broglie wavelength of 1 fm. Because of the higher wavelength the incident neutrons are more likely to interact with a single nucleon through direct nuclear processes. In stellar nucleosynthesis the energies involved are generally at most in the 5 MeV range, but typically far less. B. The Hauser-Feshbach Statistical Model With the formation of the compound nucleus at less energetic excitation levels the nuclear reactions proceed through narrow resonances. Resonances are a systematic excitation of the nucleus that go up in quantified steps instead of as a continuous spectrum. These resonances range in width from a few ev to several kev. These resonances correspond to nuclear states above the bound region. As the excitation energy increases, the spacings between the resonances decreases, eventually leading to the point where resonances are too tightly packed together to so that the specification of individual resonance properties is not possible. In order to analyze and predict what happens with the cross section, statistical models are used. These statistical models take the myriad of factors that influence the cross section and produce modeled cross sections. One of the statistical models used in statistical nuclear theory is the Hauser-Feshbach formula (see reference 8). This formula is given by: j k E j = ƛj T j J T k J g W J J g I g j J, T tot J where j is the incident particle, k is the outgoing particle, jk E j ƛj gi gj gj T j J T k J T tot J W J the average cross section for the reaction. The average is taken over an energy range that contains several compound nuclear resonances of spin and parity. 1 wavelength related to the wave number by ƛ j =. kj For n, p, particles, k j in the center of mass frame is k j= M U A j E j ℏ the statisical weight, J I 1 of the target. the statisical weight, J j 1 of the incident light particle. For photons g j =1. the statisical weight, J 1 of the compound state. the total transmission coefficient for forming the state J in the compound nucleus at energy E j. the total transmission coefficient for forming the state J in the compound nucleus at E k. the sum of all transmission functions related to decay of the state of interest. width fluctuation corrections (WFC). These define correlation factors with which all partial channels of incoming energy j and outgoing particle k, passing through excited state (E, J, ), should be multiplied.
Looking at the Hauser-Feshbach formula in parts we see that: ƛ j I k g J T j J is g g j J, T J T tot J for forming the compound nucleus in state J with incident paricle j. And is the probability that the compound nucleus in state J will decay by emitting particle k. This formulation of Hauser-Feshbach is for the binary reaction (j,k). The Hauser Feshbach formula can be modified such that it can allow for multiple particle emission. This requires multiple compound steps. Of prime importance to our studies at present is the T factor found within. At the lower energies when particle transmission is impossible/highly improbable the T tot is dominated by the photon transmission coefficient. Also, for capture reactions, T is in the numerator of Hauser-Feshbach, so ~ T. (See references 4 and 6 for further information on Hauser-Feshbach.) C. Nuclear Level Density There are several different models for nuclear structure. A few of these models are the shell model, the liquid-drop model, and the interacting boson model. (Nuclear Physics) The shell model at its simplest level predicts that nuclei having closed (completely occupied) shells of protons and neutrons should be unusually stable-as is, in fact, observed (Nuclear Physics p. 37). This fact is observed in nature. This trait is analogous with the chemical analysis of the noble gases that have filled outer electron shells and are non reactive. The nuclear level density, tot E x, J,, is defined as the number of excited nuclear states with spin, J, and parity,, per MeV around the excitation energy E x. The total level density is the sum of ll nuclear states around a given energy, i.e. tot E x = E x, J, J When these level densities are analytically expressed they are generally factorized by: E x, J, = P E x, J, R E x, J tot E x with P E x, J, being the parity distribution, and generally is taken to be ½, and with R E x, J being representing the spin distribution. The specific model that is incorporated into the TALYS code and that we will be using is the Fermi Gas Model. The Backshifted Fermi Gas Model (FGM) is based on the assumption of evenly spaced single particle excitations. Collective excitations, or the excitations of multiple particles are not considered.
Assuming that the projections of total angular momentum are randomly coupled, the FGM level density is: F E x, J, = 1 J 1 J 1 e 3 1 e au 1 4 a U 5 4 with the ½ in the front being P E x, J,, and being the spin-cutoff parameter. a is the level density parameter, and U is the and U = E with being the backshift related to the pairing energy. Using the FGM the Fermi gas distribution is given by: R F E x, J = 1 J J 1 e using this definition to sum over all F E x, J, we get the total Fermi gas level to be: tot F E x = 1 e au 1 a 14 U 54 showing that tot, the spin-cutoff F E x is dependent on the level density parameter a, and parameter. Energy-dependent shell effects are taken into account by making the level density parameter, a, energy dependent. This formulation is: a=a E x = a 1 W U 1 e U where a is the asymptomatic level density value obtained in the absence of any shell effects (i.e. a=a E x, and W is the shell corrrection energy. The asymptotic value a is typically parameterised by a= A A /3 where A is the atomic mass number of the element in question, and and are parameters that that have been chosen to give the best average level density description over a large range of nuclei. can be related to the undeformed moment of inertia, I 0, and the thermodynamic temperature, t. This is related by = = I 0 t. In this is the parallel spin cut-off parameter, or the projection of the angular momentum onto the spin axis. Due to the fact that /t suffers from shell effects and is not constant, is rewritten as: m0 R A a 5 = = F E x = I 0 t, or substituting in a : I 0= a ℏ c
R=1.A 1/3 is the radius, and m0 is the neutron mass in AMU's. This can be rewritten as: F E x =0.01389 D. 5 /3 A a au Particle and Photon Transmission Coefficients At sufficiently low incident neutron energies, the average radiative capture width, Γ γ, is due entirely to the s-wave interaction, and it is Γγ at the neutron separation energy Sn that is often used to normalize gamma-ray transmission coefficients. (Gardner, p. 6) The gamma-ray strength function is related to the photon transmission coefficient by: T XL = L 1 f XL because T XL is directly dependent on f XL the normalization of f XL is of prime importance to the photon transmission coefficient. When normalizing the gamma-ray strength function, there are several ways to model the strength function. The 5 models that we will be considering are the Blatt-Weisskopf method, using a BrinkAxel Lorentzian, a Kopecky-Uhl generalized Lorentzian, the Hartree-Fock BCS tables, or the HartreeFock Bogolyubov tables. D-1. Blatt-Weisskopf Use of the Blatt-Weisskopf is f E1 =constant. While at higher other levels, E, M, etc., the BlattWeisskopf may be a sufficient model for f E, f M and so on, but it is not a sufficient model at f E1. D-. Brink-Axel Lorentzian The Brink-Axel model describes the standard Lorentzian form of the transmission coefficient at the giant dipole resonance and is calculated by: f Xl E = K Xl Xl E Xl E E Xl E Xl where Xl is the strength of the dipole resonance, E Xl is the energy, and Xl is the width of the dipole resonance. And K Xl is 1 K Xl = l 1 ℏ c Use of the Brink-Axel Lorentzian is the commonly used model for all other transmissions besides for M1.
D-3. Kopecky-Uhl generalized Lorentzian The general way that many models depict the photon transmission for E1 radiation is through the use of a Kopecky-Uhl generalized Lorentzian. This is calculated by: f E1 E, T = K E1 [ E E1 E 0.7 E1 4 T ] E1 E1 E E E1 E E1 E E 3E1 where E1, E1, and E E1 are the peak, width, and energy of the giant dipole resonance of the nucleus E1 is the energy dependent damping and is given by: in question. E1 = E1 E 4 T E E1 and T, the nuclear temperature: T= E n S n E a S n E n is the incident neutron energy, S n is the neutron seperation energy, and is the pairing connection. D-4. Hartree-Fock BCS & Hartree-Fock-Bogolyubov tables The last two ways of modeling the E1 strength function is to allow for microscopic corrections (Goriely et al). Using the Hartree-Fock Method the E1 strength function is calculated by: GDR / E f L E, E i = E E i GDR / E where GDR is the giant dipole resonance width and is taken from experimental data when experimental data is to be had, otherwise is taken for empirical statistics. Using the BCS tables with the Hartree-Fock Method or combining Hartree-Fock with the Bogolyubuv method leads to sight perturbations in the calculations of the transmission coefficient, but as will be seen in the data, the perturbations are are only slight. D-5. Normalization of E1 When normalizing the gamma ray transmission coefficient it can be either normalized to the average radiation widths, or to the Maxwellian averaged cross section. D-5a. Radiation Widths When normalizing to the radiation widths, on most isotopes the radiative widths, GDR, is measured. For unmeasured radiation widths on unstable isotopes, the average radiation widths are calculated by:
J 1 1 J 1 B n, J B n, J 0= J 1 J 1 where J is the spin of the target nucleus and F. 1 B n, J =. Maxwellian Averaged Cross Section Another way of normalizing the E1 strength function is to normalize to the Maxwellian-averaged cross section. The Maxwellian-averaged cross section is the reaction rate < > divided by the mean velocity v T = kt/ at a given temperature T. (Hoffman p. 18). μ is the reduced mass and k is Boltzman's constant. What the Maxwellian-averaged cross sections endeavor to do is to analyze a thermally averaged cross section set for a group of atoms. This becomes of prime importance in astrophysical studies. The Maxwellian-averaged cross section reduces to: < > = vt n d 0 vt n E W E, kt de kt 0 where W E, kt =E e E/ kt and E is the center of mass energy. =
3. Code 3A. TALYS In order to calculate the cross sections relevant to the study found herein, the TALYS nuclear reaction code was used. TALYS gives us a wide range of control over the inputs into the Hauser-Feshbach statistical model. The TALYS code can either be used with a variety of different options, or can be used in a black-box mode where standardized global inputs are used. In this latter mode, it is possible to generate a cross section very easily with minimal input by the user. For the studies contained herein we used TALYS in a primarily black-box mode, altering only the E1 strength function. A basic TALYS input file is as follows: projectile n element Fe mass 56 energy 14 These four lines are all that is needed to run up a basic cross section. The line projectile tells TALYS what the incident light particle is (n, p, alpha, etc...). On the element line we define what element the target is by using the nomenclature found on the periodic table. Mass is the target's mass where we define which isotope of the element we are using. Finally the energy line lets us know what energies we are using for our reaction. These energies are given in MeV. For our studies we wished to calculate our cross sections over a range of energies ranging from 10 ev to 0 MeV. Also, we wanted to test the effects of the different models for the photon transmission coefficient. In order to do this our input file looked like: projectile n element ca mass 40 energy erange strength 1 Here all the inputs are the same as above, except that the file erange contained our range of energies and the line strength. Even though on the line energy we do not contain on specific energy, but rather a file that contains a range of energies, these values are still considered blackbox making the only change being that of the E1 strength function. What the strength key does is it allows us to define which strength function for the E1 transmission coefficient we will use. A value of 1 specifies a Kopecky-Uhl generalized Lorentzian. Value specifies a Brink-Axel Lorentzian. Value 3 uses the Hartree-Fock BCS tables, and value 4 uses the Hartree-Fock-Bogolyubov tables. (See reference 6 for a complete listing of all TALYS input commands).
In order to quickly and efficiently run our code a wrapper was used to generate the individual input files from Z=1 to Z=84. The different strength functions were used on all the isotopes tested in order to see the affect that they had upon the calculations. These cross sections were later turned into Maxwellian-averaged cross sections and compared to experimental data. The other use for the wrapper is that most calculations using TALYS are done for one incident energy and take very little time. Because we are calculating cross sections over a range of energies, the code takes a lot longer to run. What the wrapper does is it distributes the jobs over a series of Beowulf cluster nodes and allows for multiple cross sections to be calculated at the same time. 3B. MACS+ After TALYS has calculated the cross sections, it is necessary to convert these cross sections into the thermally averaged Maxwellian averaged cross sections. To do this a code written by Dr. Kevin Kelley is used. This code is called macs+. This code was developed during Dr. Kelley's time at Lawrence Livermore National Laboratory (LLNL). This code as originally made to be used with the STAPRE nuclear reaction code, but in conjunction with the wrapper, can be used to convert cross sections produced with TALYS into Maxwellian averaged cross sections. In order to produce a MACS, an input file looks like: macs+ n-08410-000.tot.int 10 where macs+ calls the code, n-08410-000.tot.int is the interpolated cross section produced by the TALYS wrapper, and 10 is the atomic mass of the initial heavy particle. When the code runs it produces a *.ps graph of the file with experimental data points graphed along with the systematic calculation.
4. Effect of the Photon Transmission Coefficient Provided below will be an analysis of the effect of the photon transmission coefficient on the Maxwellian averaged cross section. We will be looking at the overall systematic and how well each model globally fits to experimental data. In the plots that follow the data for Nitrogen 14 has been left out because on a global basis, using all 4 models for the E1 strength function the MACS for Nitrogen 14 was off by over a factor of 80 when compared to experimental data. For a full listing of all data and graphs the reader is referred to the appendixes. 4A. Brink-Axel Lorentzian Figure 1: Global Comparison of calculated MACS vs. experimental MACS Brink-Axel Lorentzian As can be seen from the plot above of the ratio of calculated MACS over the experimental MACS for the use of a Brink-Axel Lorentzian, the data is reasonably good, with a few outliers. But even the data points that are close to a ratio of 1, there are still many that are off by a factor of or 3. Looking at a specific cross section, in this case (and the case for al strength functions that we will be
comparing at this time) we will use Nickel 61. The MACS for Nickel 61 using the Brink-Axel Lorentzian is: The plot here is a logarithmic plot of the cross section (in millibarns) versus the energy (in MeV). By observing the graph we can see that the systematic is close to the measured data, but is still high, at some points by a factor of or 3. 4B. Kopecky-Uhl Generalized Lorentzian The Kopecky-Uhl generalized lorentzian is similar in calculation to the Brink-Axel Lorentzian, except that it allows for energy and width fluctuations and corrections, but it still has a general Lorentzian shape. Looking at the data for Nickel 61 using the Kopecky-Uhl Lorentzian (see figure 3 on next page) it can be seen that the data is roughly the same as when the Brink-Axel Lorentzian was used. Looking at an overall systematic (figure 4) it can be seen that like is brother, the Brink-Axel Lorentzian, it is still off by several orders of magnitude.
Figure 3: MACS for Nickel 61 using a Kopecky-Uhl Generalized Lorentzian Figure 4: Global Comparison of calculated MACS vs. experimental MACS Kopecky-Uhl Generalized Lorentzian
By looking at these two global systematics it can be seen that while in some cases a Lorentzian is an adequate model for the E1 strength function, globally it does not fit very well. In order to better model the E1 strength function, other models must be looked at. One of these models is the Hartree-Fock model. 4C. Hartree-Fock BCS Tables When calculating the E1 strength function using the Hartree-Fock method, it is customary to have preciously calculated the E1 strength functions and to have tabulated them. This is because of the myriad of different inputs that go into the Hartree-Fock method, it would considerably lengthen calculation time to calculate the E1 strength function every time. What can be seen from us of the Hartree-Fock method is a better global fit for the overall Maxwellian averaged cross section. Figure 5: Global Comparison of calculated MACS vs. experimental MACS Hartree-Fock BCS Tables First off, it can be seen that the Hartree-Fock BCS tables are more closely centered around a ratio of 1. Also, the outliers in data tend to have a lower calculated over experimental ratio than that of using a Lorentzian. Looking at the MACS for Nickel 61 we see:
Figure 6: MACS for Nickel 61 using the Hartree-Fock BCS Tables As can be immediately seen, the Hartree-Fock BCS tables are a lot more accurate on Nickel 61. Also, it can be seen that unlike the Lorentzian's, the BCS tables actually fall within the error of the measured cross sections. This is a vast improvement. 4D. Hartree-Fock-Bogolyubov Tables Lastly for our considerations is the use of the Hartree-Fock-Bogolyubuv Tables. This table is another set of calculated E1 strength functions using the Hartree-Fock method, but with slight alterations made by Bogolyubuv. Looking at Figure 7 we can see the global fit is approximately the same as the BCS tables with some minor differences between them. In the BCS tables we can see that the ratio of calculated over experimental never grow larger than a factor of about 13 or 14 while the Bogolyubuv tables have a data point at a factor of 0 times larger. But even with that, it can be seen that the rest of the outliers are tightly packed close to a ratio of 1.
Figure 7: Global Comparison of calculated MACS vs. experimental MACS Hartree-Fock Bogolyubuv Tables Looking at the data for Nickel 61 using the Bogolyubuv tables: Figure 8: MACS for Nickel 61 using the Hartree-Fock-Bogolyubuv Tables
It can be seen from figure 8, that in this case the Bogolybuv tables provided a closer fit to experimental data than the BCS tables did. While this may be the case for Nickel 61, other targets are not the same. 4E. Conclusions and Future Research From the data provided above, and from the data seen in the appendixes it can be seen that the HartreeFock Tables provide a better fit for the normalization of the photon transmission coefficient. While in many cases a generalized or even an enhanced Lorentzian may be adequate, globally speaking the Hartree-Fock method provides a better model for the E1 strength function. The differences between these four models presented show us that the E1 strength function strongly impacts the cross section for neutron capture cross section. But even with the better global fit of the E1 strength function using the Hartree-Fock method it is important to note that other models can be used for the E1 strength function, and that there are a myriad of other inputs to the Hauser-Feshbach statistical model that could possible effect the calculation of the nuclear cross section. While the research presented herein has been extremely comprehensive for an analysis of these 4 models on neutron capture cross sections, future research should be done on the influence of the other factors that go into the HF model. Also, the actual calculation of BCS and Bogolybuv tables would warrant merit in that it could be used to better calculate these tables for an improved cross section. While a lot as been learned about neutron capture cross sections, more work is still needed to better understand the calculation of nuclear cross sections.
Appendix A Calculated Cross Sections Z=1 to Z=84 #Z A Element Recommended MACS dmacs Strength1 Strength Strength3 Strength4 03 007 n-003007 07 014 n-007014 0.04000 0.041000 0.004000.95550E-03 3.71079E-03.95550E-03.95550E-03 0.060000.154701E+00 3.140149E+00.154701E+00.154701E+00 07 015 n-007015 08 016 n-008016 0.005800 0.038000 0.000500 8.55968E-03 1.47683E-0 8.55968E-03 8.55968E-03 0.004000 1.08030E-01 1.837643E-01 1.53546E-01 1.197564E-01 08 018 n-008018 09 019 n-009019 0.008900 5.800000 0.000800 1.57093E-01.756397E-01 1.953793E-01 1.779470E-01 1.00000 1.91917E+00 3.086111E+00.30383E+00.04061E+00 10 00 n-01000 10 01 n-01001 0.119000 1.500000 0.011000 1.13645E+00.31801E+00 1.648498E+00 1.409397E+00 0.900000 4.901853E+00 7.984066E+00 7.36576E+00 6.061551E+00 10 0 n-0100 11 03 n-01103 0.059000.100000 0.006000 3.194999E-01 6.938807E-01 4.400843E-01 3.95906E-01 0.00000.0618E+00 3.853830E+00.49580E+00.17631E+00 1 04 n-0104 1 05 n-0105 3.300000 6.400000 0.400000.185904E+00 5.09966E+00 3.38783E+00.798434E+00 0.400000 7.536136E+00 1.404865E+01 1.064633E+01 9.575419E+00 1 06 n-0106 13 06 n-01306 0.16000 3.700000 0.009000 9.846475E-01.71936E+00 1.4451E+00 1.404571E+00 0.000000 6.873161E+00 7.6845E+00 9.91938E+00 8.58369E+00 13 07 n-01307 14 08 n-01408 3.740000.900000 0.300000 4.845379E+00 9.100670E+00 5.596961E+00 5.311856E+00 0.300000 4.01543E+00 9.310085E+00 5.865685E+00 5.3711E+00 14 09 n-01409 14 030 n-014030 7.900000 6.500000 0.900000 9.905760E+00 1.71146E+01 1.314633E+01 1.346387E+01 0.600000 1.3466E+00 3.683474E+00 1.874111E+00 1.8781E+00 15 031 n-015031 16 03 n-01603 1.740000 4.100000 0.090000 7.180507E+00 1.460498E+01 8.77533E+00 8.048680E+00 0.00000 7.58139E+00 1.59454E+01 1.108990E+01 9.4784E+00 16 033 n-016033 16 034 n-016034 7.400000 0.6000 1.500000 1.599088E+01.667901E+01 1.919843E+01 1.836650E+01 0.010000.193083E+00 5.368666E+00.756585E+00.6483E+00 16 036 n-016036 17 035 n-017035 0.171000 10.000000 0.014000 1.471708E-01 4.594705E-01.01398E-01.06599E-01 0.300000 1.43010E+01.165878E+01 1.31547E+01 1.7988E+01 17 036 n-017036 17 037 n-017037 1.000000.150000 1.000000 1.848531E+01.9938E+01 1.908615E+01 1.83117E+01 0.080000.54961E+00 4.436195E+00.1777E+00.17156E+00 18 036 n-018036 18 038 n-018038 9.000000 3.000000 1.500000 9.709868E+00 1.95415E+01 1.15866E+01 1.104343E+01 0.300000.06786E+00 5.01069E+00.417315E+00.370714E+00 18 039 n-018039 18 040 n-018040 8.000000.600000.000000 9.36359E+00 1.985050E+01 1.099776E+01 1.030437E+01 0.00000 1.503983E+01 9.748759E+00.368398E+00.89455E+00 19 039 n-019039 19 040 n-019040 11.800000 31.000000 0.400000 1.03461E+01 1.805489E+01 9.96657E+00 9.53395E+00 7.000000 8.6558E+01 8.548793E+01 3.877005E+01 3.745433E+01 19 041 n-019041 0 040 n-00040.000000 6.700000 0.700000.78961E+01.49959E+01.391871E+01.8018E+01 0.700000.785843E+01.874696E+01 8.0990E+00 7.9087E+00 0 041 n-00041 0 04 n-0004 30.000000 15.600000 7.000000 6.51603E+01 5.70045E+01 3.6366E+01 3.450969E+01.000000 3.67063E+01 3.471651E+01 1.4390E+01 1.40669E+01 0 043 n-00043 0 044 n-00044 51.000000 9.400000 6.000000 7.1530E+01 6.34604E+01 4.850064E+01 4.5393E+01 1.300000 4.73586E+01 3.185991E+01 8.4145E+00 8.151855E+00 0 045 n-00045 0 046 n-00046 17.500000 5.300000 3.500000 6.64189E+01 5.70471E+01 1.64980E+01 1.67801E+01 0.500000 1.880598E+01 1.613899E+01.43849E+00.483811E+00 0 048 n-00048 1 045 n-01045 0.870000 69.000000 0.090000 7.858999E+00.196957E+00 6.09550E-01 6.71074E-01 5.000000 8.838400E+01 8.510768E+01 6.09630E+01 5.85341E+01 046 n-0046 047 n-0047 6.799999 64.40000 3.00000 4.34441E+01 3.14693E+01.804309E+01.77045E+01 7.700000 1.09589E+0 9.796895E+01 8.563709E+01 8.51510E+01 048 n-0048 049 n-0049 31.799999.100000 5.500000 4.87850E+01 3.8433E+01 1.01941E+01 1.30301E+01.100000 3.768596E+01 3.30453E+01.385444E+01.48474E+01 050 n-0050 3 050 n-03050 3.600000 50.000000 0.400000 1.63330E+01 5.16878E+00.67934E+00.855339E+00 9.000000 5.37787E+01 4.55015E+01.979338E+01 3.81595E+01 3 051 n-03051 4 050 n-04050 38.000000 49.000000 4.000000 6.55881E+01 4.99466E+01 1.5973E+01 1.330563E+01 13.000000 7.153080E+01 5.481053E+01.73711E+01.81849E+01
#Z A Element Recommended MACS dmacs Strength1 Strength Strength3 Strength4 4 051 n-04051 4 05 n-0405 87.000000 8.800000 16.000000 1.688954E+0 1.533096E+0 7.164184E+01 7.4003E+01.300000 3.744530E+01.37686E+01 1.6835E+01 1.34897E+01 4 053 n-04053 4 054 n-04054 58.000000 6.700000 10.000000 5.43665E+01 4.317466E+01.469698E+01.544091E+01 1.600000 4.040600E+01.175976E+01 6.17091E+00 6.353194E+00 5 055 n-05055 6 054 n-06054 39.599998 7.600000 3.000000 5.485488E+01 5.00533E+01 3.303167E+01 3.414599E+01 1.800000 6.5937E+01 4.994753E+01 4.97879E+01 4.55139E+01 6 055 n-06055 6 056 n-06056 75.000000 11.700000 1.000000 1.63730E+0 1.504868E+0 8.401E+01 8.635303E+01 0.500000 3.1043E+01.138931E+01.38555E+01.330776E+01 6 057 n-06057 6 058 n-06058 40.000000 1.100000 4.000000 5.834891E+01 4.6707E+01 3.443636E+01 3.510017E+01 1.300000 6.78011E+01 5.531710E+01 1.350419E+01 1.501097E+01 7 059 n-07059 8 058 n-08058 38.000000 41.000000 4.000000 7.374050E+01 6.567153E+01 3.0791E+01 3.394058E+01.000000 1.06438E+0 8.511571E+01 5.303654E+01 5.543875E+01 8 059 n-08059 8 060 n-08060 87.000000 30.000000 14.000000 1.5101E+0 1.396904E+0 1.105955E+0 1.7019E+0 3.000000 8.04600E+01 5.897483E+01.757181E+01.939778E+01 8 061 n-08061 8 06 n-0806 8.000000 1.500000 8.000000 1.38715E+0 1.818E+0 8.936667E+01 8.9470E+01 4.000000 4.655475E+01.966956E+01 1.473717E+01 1.5679E+01 8 063 n-08063 8 064 n-08064 31.000000 8.700000 6.000000 9.33369E+01 8.33387E+01 4.508896E+01 4.1560E+01 0.900000 8.17137E+01 4.9015E+01 7.40784E+00 7.909033E+00 9 063 n-09063 9 065 n-09065 94.000000 41.000000 10.000000 8.7896E+01 7.94566E+01 7.035903E+01 7.309550E+01 4.000000 5.70796E+01 5.18380E+01 3.348197E+01 3.33104E+01 30 064 n-030064 30 065 n-030065 59.000000 16.000000 5.000000 1.05674E+0 9.66618E+01 6.305903E+01 6.38576E+01 7.000000.459910E+0.41764E+0 1.75997E+0 1.60013E+0 30 066 n-030066 30 067 n-030067 35.000000 153.000000 3.000000 5.968033E+01 4.897438E+01 3.040866E+01.966940E+01 15.000000 1.553175E+0 1.491037E+0 1.118883E+0 1.0169E+0 30 068 n-030068 30 070 n-030070 19.00001 1.500000.400000 4.385069E+01 3.746901E+01 1.587070E+01 1.636678E+01.000000 3.947175E+01.798817E+01 8.43075E+00 8.4108E+00 31 069 n-031069 31 071 n-031071 139.000000 13.000000 6.000000 1.179988E+0 1.146443E+0 1.11663E+0 1.095163E+0 8.000000 1.044145E+0 1.044546E+0 6.9677E+01 7.010715E+01 3 070 n-03070 3 07 n-0307 88.000000 73.000000 5.000000 1.080113E+0 9.79894E+01 7.616943E+01 7.3970E+01 7.000000 7.418167E+01 7.041314E+01 5.777410E+01 5.695501E+01 3 073 n-03073 3 074 n-03074 43.000000 53.000000 47.000000 3.04485E+0 3.05458E+0 1.398185E+0 1.66937E+0 7.000000 5.30760E+01 4.751698E+01 3.93887E+01 4.111917E+01 3 076 n-03076 33 075 n-033075 33.000000 568.000000 15.000000.7634E+01.4040E+01 1.916E+01.088188E+01 35.000000 3.874680E+0 3.841937E+0.516309E+0.58688E+0 34 074 n-034074 34 076 n-034076 67.000000 164.000000 5.000000.78157E+0.733805E+0 1.847805E+0 1.811391E+0 8.000000 1.607104E+0 1.5458E+0 8.36030E+01 8.757554E+01 34 077 n-034077 34 078 n-034078 418.000000 109.000000 71.000000 4.60896E+0 4.540357E+0.518895E+0.608081E+0 41.000000 7.005849E+01 6.558743E+01 6.558716E+01 6.89856E+01 34 079 n-034079 34 080 n-034080 63.000000 4.000000 46.000000 4.06985E+0 4.60793E+0 1.77846E+0 1.714859E+0 3.000000 7.009468E+01 6.56551E+01.688449E+01.765755E+01 34 08 n-03408 35 079 n-035079 9.000000 67.000000 8.000000.801018E+01 3.838009E+01 1.037565E+01 1.49078E+01 4.000000 5.645390E+0 5.60300E+0 4.344806E+0 4.37434E+0 35 081 n-035081 36 078 n-036078 313.000000 31.000000 16.000000 3.4865E+0 3.368954E+0 1.58374E+0 1.644633E+0 6.000000 3.50504E+0 3.440105E+0.381065E+0.45514E+0 36 079 n-036079 36 080 n-036080 959.000000 67.000000 16.000000 8.90490E+0 8.87866E+0 5.436783E+0 5.444833E+0 14.000000 3.05553E+0.9850E+0 1.338318E+0 1.357771E+0 36 081 n-036081 36 08 n-03608 607.000000 90.000000 105.000000 8.64097E+0 8.66358E+0 5.53975E+0 5.050307E+0 6.000000 1.470170E+0 1.33398E+0 6.56701E+01 6.565080E+01 36 083 n-036083 36 084 n-036084 43.000000 38.000000 15.000000 1.69379E+0 1.67759E+0 1.0600E+0 1.157735E+0 4.000000 1.111176E+0 1.108748E+0.71871E+01 3.080640E+01 36 085 n-036085 36 086 n-036086 55.000000 3.400000 45.000000 1.503139E+0 1.54883E+0 5.065403E+01 5.945589E+01 0.300000 9.051975E+00 1.5806E+01 3.917190E+00 4.758818E+00
#Z A Element Recommended MACS dmacs Strength1 Strength Strength3 Strength4 37 085 n-037085 37 086 n-037086 40.000000 0.000000 9.000000 1.84084E+0 1.8700E+0 1.9800E+0.159947E+0 163.000000 3.4359E+0 3.54374E+0.531371E+0.85047E+0 37 087 n-037087 38 084 n-038084 15.500000 368.000000 0.500000.7959E+01.950970E+01 1.503415E+01 1.84444E+01 16.000000 3.516711E+0 3.389369E+0 1.740506E+0 1.89715E+0 38 086 n-038086 38 087 n-038087 64.000000 9.000000 3.000000 6.9710E+01 6.001610E+01 4.58437E+01 5.07383E+01 4.000000 1.567945E+0 1.508619E+0 8.8410E+01 1.030806E+0 38 088 n-038088 38 089 n-038089 6.00000 19.000000 0.300000 8.60991E+00 1.35119E+01 4.98689E+00 5.7139E+00 14.000000 3.5915E+01 4.8145E+01 1.5151E+01 1.591780E+01 39 089 n-039089 40 090 n-040090 19.000000 1.000000 0.600000 1.53860E+01 1.706384E+01 1.606710E+01 1.893509E+01.000000 1.99647E+01.50095E+01 1.304110E+01 1.63077E+01 40 091 n-040091 40 09 n-04009 60.000000 33.000000 8.000000 4.790004E+01 5.496385E+01 4.61E+01 4.837974E+01 4.000000.979778E+01 3.839787E+01.474197E+01.41180E+01 40 093 n-040093 40 094 n-040094 95.000000 6.000000 10.000000 1.531388E+0 1.65507E+0 5.1631E+01 5.476767E+01 1.000000.345E+01 3.3737E+01.4561E+01 1.915371E+01 40 095 n-040095 40 096 n-040096 79.000000 10.700000 1.000000 1.05649E+0 1.57551E+0 3.145813E+01 3.106335E+01 0.500000 3.398477E+01 4.745811E+01 9.79010E+00 9.39777E+00 41 093 n-041093 41 094 n-041094 66.000000 48.000000 5.000000.66758E+0.6978E+0 1.95504E+0 1.371554E+0 9.000000 5.351777E+0 5.348939E+0.171103E+0.14769E+0 41 095 n-041095 4 09 n-0409 310.000000 70.000000 65.000000 4.948683E+0 4.985308E+0 1.809135E+0 1.801969E+0 10.000000 5.039633E+01 6.10939E+01 3.669867E+01 4.34537E+01 4 094 n-04094 4 095 n-04095 10.000000 9.000000 0.000000 7.56184E+01 8.643731E+01 6.418711E+01 7.19889E+01 1.000000.355989E+0.476548E+0 1.71070E+0 1.566365E+0 4 096 n-04096 4 097 n-04097 11.000000 339.000000 8.000000 7.45053E+01 8.598748E+01 7.643011E+01 7.591769E+01 14.000000.75187E+0.787508E+0 1.930559E+0 1.707879E+0 4 098 n-04098 4 099 n-04099 99.000000 40.000000 7.000000 6.43437E+01 7.195748E+01 4.854471E+01 4.997304E+01 40.000000 3.44851E+0 3.51400E+0.850E+0 1.594615E+0 4 100 n-04100 43 099 n-043099 108.000000 781.000000 14.000000 8.148736E+01 8.656E+01 5.340111E+01 5.718398E+01 50.000000 1.189483E+03 1.190918E+03 4.146587E+0 4.194319E+0 44 096 n-044096 44 098 n-044098 38.000000 173.000000 60.000000 9.097681E+01 1.08840E+0 9.430406E+01 1.081347E+0 36.000000 1.8870E+0 1.40955E+0 1.086097E+0 1.16901E+0 44 099 n-044099 44 100 n-044100 631.000000 06.000000 99.000000 8.501904E+0 8.53481E+0 5.37430E+0 5.50894E+0 13.000000 1.509334E+0 1.587550E+0 1.58380E+0 1.368451E+0 44 101 n-044101 44 10 n-04410 996.000000 186.000000 40.000000 1.063E+03 1.037416E+03 4.560906E+0 4.433466E+0 11.000000 1.14441E+0 1.17646E+0 1.005145E+0 1.056940E+0 44 103 n-044103 44 104 n-044104 343.000000 161.000000 5.000000 5.698919E+0 5.740394E+0.36313E+0.35607E+0 10.000000 1.753536E+0 1.81185E+0 1.037711E+0 1.1380E+0 45 103 n-045103 46 10 n-04610 811.000000 375.000000 14.000000 8.19718E+0 8.091658E+0 3.775034E+0 4.04099E+0 118.000000 1.74379E+0 1.859706E+0.003868E+0.008484E+0 46 104 n-046104 46 105 n-046105 89.000000 100.000000 9.000000.718789E+0.815796E+0 1.760884E+0 1.90076E+0 60.000000 1.51158E+03 1.53508E+03 6.915013E+0 7.017331E+0 46 106 n-046106 46 107 n-046107 5.000000 1340.000000 5.000000.39938E+0.4376E+0 1.10469E+0 1.175956E+0 60.000000 1.079515E+03 1.078911E+03 5.487463E+0 5.6464E+0 46 108 n-046108 46 110 n-046110 03.000000 146.000000 0.000000 3.4337E+0 3.301611E+0 1.645439E+0 1.814470E+0 0.000000.39743E+0.41085E+0 7.665943E+01 9.366099E+01 47 107 n-047107 47 109 n-047109 79.000000 788.000000 30.000000 8.518655E+0 8.438953E+0 4.66730E+0 5.06719E+0 30.000000 1.13849E+03 1.118306E+03 4.84501E+0 5.46441E+0 47 110 n-047110 48 106 n-048106 117.000000 30.000000 188.000000 1.488679E+03 1.484690E+03 1.09415E+03 1.060548E+03 4.000000 4.901854E+0 5.03380E+0.678343E+0 3.049586E+0 48 108 n-048108 48 110 n-048110 0.000000 46.000000 9.000000 4.081385E+0 4.130889E+0 1.89646E+0 1.9011E+0 10.000000.464537E+0.508780E+0 1.638601E+0 1.790785E+0 48 111 n-048111 48 11 n-04811 1063.000000 35.000000 15.000000 7.6348E+0 7.660639E+0 5.464073E+0 5.116317E+0 30.000000.9854E+0.309516E+0 1.038486E+0 1.131841E+0
#Z A Element Recommended MACS dmacs Strength1 Strength Strength3 Strength4 48 113 n-048113 48 114 n-048114 78.000000 17.000000 80.000000 9.014435E+0 9.050363E+0 4.315938E+0 4.094047E+0 5.000000 1.3655E+0 1.444470E+0 7.35886E+01 7.794953E+01 48 115 n-048115 48 116 n-048116 90.000000 59.000000 6.000000 5.9363E+0 5.988341E+0 3.346607E+0 3.135363E+0.000000 8.38394E+01 8.949576E+01 6.479967E+01 6.831049E+01 49 113 n-049113 49 114 n-049114 787.000000 595.000000 70.000000 6.153801E+0 6.144808E+0 4.515579E+0 4.775574E+0 1300.000000 1.510678E+03 1.507794E+03 9.881434E+0 1.078804E+03 49 115 n-049115 50 11 n-05011 706.000000 10.000000 70.000000 7.93709E+0 7.937E+0 4.064601E+0 4.43977E+0 1.000000 3.17976E+0 3.66430E+0 1.667597E+0 1.855568E+0 50 114 n-050114 50 115 n-050115 134.399994 34.399994 1.800000 1.76876E+0 1.883349E+0 9.647840E+01 1.074683E+0 8.700000 6.149691E+0 6.167798E+0 3.79480E+0 3.718396E+0 50 116 n-050116 50 117 n-050117 91.40000 319.000000 0.900000 9.048044E+01 9.763746E+01 7.71653E+01 9.011374E+01 5.000000 3.161358E+0 3.197480E+0.470691E+0.76169E+0 50 118 n-050118 50 119 n-050119 6.099998 180.000000 0.600000 1.8970E+0 1.431959E+0 4.566538E+01 5.53978E+01 10.000000.19589E+0.1691E+0 1.605806E+0 1.75495E+0 50 10 n-05010 50 11 n-05011 36.000000 167.000000 0.500000 4.815716E+01 5.78691E+01.966043E+01 3.4616E+01 30.000000 3.375763E+0 3.405187E+0 1.708319E+0 1.960096E+0 50 1 n-0501 50 14 n-05014 1.900000 1.000000 1.500000 4.57508E+01 5.18857E+01.498783E+01 3.068638E+01 1.800000 1.909561E+01.87571E+01 9.338586E+00 1.141340E+01 50 15 n-05015 50 16 n-05016 59.000000 10.000000 9.000000 7.47571E+01 7.50417E+01 5.50196E+01 6.869406E+01 4.000000 9.155574E+00 1.8885E+01 9.480113E+00 1.64401E+01 51 11 n-05111 51 1 n-0511 53.000000 894.000000 16.000000 6.059400E+0 6.038875E+0 3.901085E+0 4.066E+0 16.000000 1.48415E+03 1.44183E+03 8.64756E+0 9.3438E+0 51 13 n-05113 51 15 n-05115 303.000000 60.000000 9.000000 4.36979E+0 4.338577E+0.755149E+0 3.165815E+0 70.000000.4040E+0.386838E+0 1.584E+0 1.55949E+0 5 10 n-0510 5 1 n-051 40.000000 95.000000 103.000000 4.7486E+0 4.86746E+0.68419E+0.871390E+0 3.000000 3.780151E+0 3.863610E+0 1.698887E+0 1.75757E+0 5 13 n-0513 5 14 n-0514 83.000000 155.000000 8.000000 8.18760E+0 8.099985E+0 5.10757E+0 5.17917E+0.000000.635873E+0.706537E+0 1.09519E+0 1.67941E+0 5 15 n-0515 5 16 n-0516 431.000000 81.300003 4.000000 5.090803E+0 5.083938E+0.341884E+0.606088E+0 1.400000 1.430035E+0 1.56098E+0 6.064378E+01 7.07574E+01 5 18 n-0518 5 130 n-05130 44.40000 14.700000 1.300000 7.655808E+01 8.4633E+01 5.346E+01 6.694398E+01.800000 4.313559E+01 4.708765E+01.37313E+01 3.17603E+01 53 17 n-05317 53 19 n-05319 635.000000 441.000000 30.000000 5.18946E+0 5.173630E+0 3.94764E+0 4.73975E+0.000000 3.3179E+0 3.18393E+0.787776E+0 3.5031E+0 54 14 n-05414 54 16 n-05416 644.000000 359.000000 83.000000 6.014657E+0 6.008845E+0 3.74387E+0 4.086941E+0 51.000000 3.817388E+0 3.86135E+0.7756E+0.5556E+0 54 18 n-05418 54 19 n-05419 48.000000 47.000000 66.000000 1.779187E+0 1.89666E+0 1.383899E+0 1.64903E+0 71.000000 4.137006E+0 4.1180E+0.810340E+0 3.4145E+0 54 130 n-054130 54 131 n-054131 141.000000 340.000000 51.000000 1.783944E+0 1.860307E+0 8.91510E+01 1.117097E+0 65.000000 3.086385E+0 3.103597E+0.04650E+0.59947E+0 54 13 n-05413 54 133 n-054133 64.599998 17.000000 5.300000 7.31544E+01 8.04666E+01 4.81370E+01 5.334557E+01 34.000000 8.713935E+01 8.84544E+01 1.338477E+0 1.647699E+0 54 134 n-054134 54 136 n-054136 0.00001 0.910000 1.700000 3.808390E+01 4.74640E+01.170638E+01.834911E+01 0.080000 6.78181E+00 4.905751E+00 1.050990E+00 1.69103E+00 55 133 n-055133 55 134 n-055134 509.000000 664.000000 1.000000 5.135665E+0 5.119769E+0 3.881684E+0 4.946060E+0 174.000000 7.963199E+0 7.944494E+0 4.19048E+0 5.90538E+0 55 135 n-055135 56 130 n-056130 198.000000 760.000000 17.000000 1.5685E+0 1.51955E+0 1.595879E+0.079998E+0 110.000000 4.716471E+0 4.753376E+0.634507E+0 3.035036E+0 56 13 n-05613 56 134 n-056134 379.000000 176.000000 137.000000.766689E+0.8956E+0 1.580194E+0 1.9939E+0 5.600000 1.156369E+0 1.3767E+0 8.493716E+01 1.063468E+0 56 135 n-056135 56 136 n-056136 455.000000 61.00001 15.000000 3.93851E+0 3.949739E+0.759311E+0 3.30054E+0.000000 5.4791E+01 6.199535E+01 3.751630E+01 4.568145E+01
56 137 n-056137 76.300003.400000 6.41660E+01 6.570678E+01 7.90880E+01 9.647799E+01 56 138 n-056138 57 139 n-057139 4.000000 38.40000 0.00000 3.998870E+00 3.063980E+00.34353E+00 3.30318E+00.700000 4.60915E+01 4.355745E+01.389887E+01 3.470769E+01 58 13 n-05813 58 133 n-058133 1570.000000 600.000000 40.000000 8.705195E+0 8.691139E+0 5.57539E+0 5.9666E+0 400.000000 1.915179E+03 1.911660E+03 1.558165E+03 1.736733E+03 58 134 n-058134 58 135 n-058135 967.000000 130.000000 351.000000 5.988E+0 5.91669E+0.773964E+0 3.476671E+0 60.000000 1.088561E+03 1.08601E+03 7.467759E+0 8.973634E+0 58 136 n-058136 58 137 n-058137 300.000000 973.000000 1.000000 4.16163E+0 4.174981E+0.08730E+0.578750E+0 56.000000 8.587399E+0 8.559975E+0 6.948094E+0 8.3576E+0 58 138 n-058138 58 139 n-058139 179.000000 14.000000 5.000000 1.719111E+0 1.77518E+0 1.047597E+0 1.30343E+0 10.000000.86434E+0.865595E+0.081797E+0.668863E+0 58 140 n-058140 58 141 n-058141 11.000000 76.000000 0.400000 1.17464E+01 1.061947E+01 6.990414E+00 9.69866E+00 33.000000 1.500967E+0 1.4704E+0 5.810698E+01 7.545567E+01 58 14 n-05814 59 141 n-059141 8.000000 111.40000 1.000000 4.381609E+01 3.80668E+01 1.607477E+01.006065E+01 1.400000 1.47088E+0 1.07935E+0 5.4644E+01 7.345867E+01 59 14 n-05914 59 143 n-059143 415.000000 350.000000 178.000000 3.81084E+0 3.77680E+0.003761E+0.65806E+0 86.000000 3.77776E+0 3.747751E+0 1.7646E+0.43549E+0 60 14 n-06014 60 143 n-060143 35.000000 45.000000 0.700000 4.53646E+01 4.377671E+01.400936E+01 3.197416E+01 3.000000 3.004374E+0.966784E+0 1.399059E+0 1.73545E+0 60 144 n-060144 60 145 n-060145 81.300003 45.000000 1.500000 6.70935E+01 6.39687E+01 4.694993E+01 4.97111E+01 5.000000 5.10585E+0 5.064816E+0.407340E+0.501368E+0 60 146 n-060146 60 147 n-060147 91.199997 544.000000 1.000000 1.0891E+0 1.0130E+0 4.10568E+01 5.044404E+01 90.000000 1.05583E+03 1.199483E+03 3.804508E+0 4.41151E+0 60 148 n-060148 60 150 n-060150 147.000000 159.000000.000000 1.478503E+0 1.445884E+0 7.8180E+01 9.919374E+01 10.000000 1.783438E+0 1.758196E+0 6.359759E+01 6.537818E+01 61 147 n-061147 61 148 n-061148 190.000000 970.000000 470.000000 1.03146E+03 1.07554E+03 3.566787E+0 4.650758E+0 500.000000 1.634145E+03 1.67355E+03 8.70018E+0 1.018759E+03 61 149 n-061149 6 144 n-06144 510.000000 9.000000 750.000000 1.64487E+03 1.637386E+03 4.555431E+0 6.010540E+0 6.000000 7.546566E+01 7.474403E+01 4.916358E+01 6.46971E+01 6 147 n-06147 6 148 n-06148 973.000000 41.000000 10.000000 1.068470E+03 1.06373E+03 5.00557E+0 5.55148E+0.000000.519940E+0.483496E+0 1.094160E+0 1.30635E+0 6 149 n-06149 6 150 n-06150 180.000000 4.000000 17.000000 1.736638E+03 1.79368E+03 8.80431E+0 8.41430E+0 4.000000 5.040005E+0 4.998088E+0 1.89819E+0.5104E+0 6 151 n-06151 6 15 n-0615 710.000000 473.000000 40.000000 3.19930E+03 3.18897E+03 1.49378E+03 1.451897E+03 4.000000 4.054797E+0 4.06417E+0.95348E+0.9036E+0 6 153 n-06153 6 154 n-06154 1095.000000 06.000000 175.000000 1.391163E+03 1.385358E+03 5.915649E+0 6.783631E+0 1.000000.56957E+0.53615E+0 9.75339E+01 1.009514E+0 63 151 n-063151 63 15 n-06315 3775.000000 7600.000000 150.000000 4.364034E+03 4.350195E+03 1.578994E+03 1.995161E+03 100.000000 6.80910E+03 6.790957E+03 3.70353E+03 4.36389E+03 63 153 n-063153 63 154 n-063154 780.000000 440.000000 100.000000 3.8438E+03 3.811898E+03 1.505439E+03 1.939590E+03 670.000000 5.17749E+03 5.116585E+03.507031E+03.94688E+03 63 155 n-063155 64 15 n-06415 130.000000 1049.000000 84.000000 1.603818E+03 1.59703E+03 7.319838E+0 7.97000E+0 17.000000 8.5980E+0 8.16380E+0 4.10018E+0 4.99681E+0 64 153 n-064153 64 154 n-064154 4550.000000 108.000000 700.000000 4.850316E+03 4.838569E+03.565700E+03.979595E+03 1.000000 1.11581E+03 1.109994E+03 4.583061E+0 5.656584E+0 64 155 n-064155 64 156 n-064156 648.000000 615.000000 30.000000 3.181913E+03 3.17009E+03 1.498685E+03 1.69679E+03 5.000000 6.88455E+0 6.84566E+0.576680E+0.816184E+0 64 157 n-064157 64 158 n-064158 1369.000000 34.000000 15.000000 1.356161E+03 1.35177E+03 5.3509E+0 5.60419E+0 3.000000 3.986337E+0 3.950700E+0 1.351159E+0 1.435007E+0 64 160 n-064160 65 159 n-065159 154.000000 1580.000000 0.000000.31107E+0.54786E+0 7.47937E+01 7.405486E+01 150.000000 1.67589E+03 1.60316E+03 7.973857E+0 8.57883E+0 65 160 n-065160 66 156 n-066156 340.000000 1567.000000 510.000000 5.653688E+03 5.638440E+03.476038E+03.60694E+03 145.000000.53360E+03.5803E+03 7.779315E+0 1.00645E+03
#Z A Element Recommended MACS dmacs Strength1 Strength Strength3 Strength4 66 158 n-066158 66 160 n-066160 1060.000000 890.000000 400.000000 9.34985E+0 9.304786E+0 4.17697E+0 5.110743E+0 1.000000 8.785675E+0 8.7388E+0 3.03186E+0 3.940497E+0 66 161 n-066161 66 16 n-06616 1964.000000 446.000000 19.000000.546613E+03.537777E+03 8.84169E+0 1.143818E+03 4.000000 5.1860E+0 5.14747E+0.58798E+0.80876E+0 66 163 n-066163 66 164 n-066164 111.000000 1.000000 11.000000 1.3749E+03 1.365858E+03 5.561885E+0 5.575477E+0 3.000000.97700E+0.93501E+0 1.3568E+0 1.94590E+0 67 163 n-067163 67 165 n-067165 15.000000 180.000000 95.000000 5.708049E+03 5.696076E+03 1.884387E+03.798E+03 100.000000 1.374094E+03 1.368448E+03 6.587605E+0 7.47987E+0 68 16 n-06816 68 164 n-068164 164.000000 1084.000000 14.000000.08878E+03.00773E+03 6.0501E+0 8.040919E+0 51.000000 1.034691E+03 1.0948E+03 4.96853E+0 5.459654E+0 68 166 n-068166 68 167 n-068167 563.000000 145.000000 56.000000 6.57709E+0 6.48367E+0.86361E+0 3.75735E+0 143.000000 1.68886E+03 1.6068E+03 6.678164E+0 7.598477E+0 68 168 n-068168 68 169 n-068169 338.000000 653.000000 44.000000 3.365373E+0 3.34060E+0 1.469104E+0 1.6681E+0 114.000000 6.118154E+0 6.076631E+0 3.045166E+0 3.145871E+0 68 170 n-068170 69 169 n-069169 170.000000 119.000000 7.000000.56696E+0.5597E+0 1.10049E+0 1.3483E+0 56.000000 8.641300E+0 8.583866E+0 4.435075E+0 5.197137E+0 69 170 n-069170 69 171 n-069171 1870.000000 486.000000 330.000000 1.930075E+03 1.93371E+03 8.167578E+0 9.056044E+0 144.000000 9.63531E+0 9.590786E+0 3.808617E+0 4.554451E+0 70 168 n-070168 70 170 n-070170 1160.000000 768.000000 440.000000 1.469331E+03 1.463475E+03 5.908447E+0 7.848039E+0 7.000000 6.311844E+0 6.70656E+0 3.146013E+0 4.131186E+0 70 171 n-070171 70 17 n-07017 110.000000 341.000000 1.000000 1.00068E+03 1.19565E+03 6.480189E+0 8.16666E+0 3.000000 4.076519E+0 4.037987E+0.106356E+0.4648E+0 70 173 n-070173 70 174 n-070174 754.000000 151.000000 7.000000 8.68509E+0 8.635811E+0 4.055580E+0 4.484199E+0.000000.41931E+0.381874E+0 1.033375E+0 1.199673E+0 70 175 n-070175 70 176 n-070176 558.000000 116.000000 83.000000 7.78369E+0 7.66904E+0.581078E+0.985073E+0.000000 1.846179E+0 1.81886E+0 9.85673E+01 1.10696E+0 71 175 n-071175 71 176 n-071176 1146.000000 153.000000 44.000000 1.619388E+03 1.613579E+03 6.944744E+0 8.56369E+0 69.000000 1.86075E+03 1.854811E+03 7.044658E+0 8.371378E+0 7 174 n-07174 7 176 n-07176 956.000000 455.000000 83.000000 8.599363E+0 8.55346E+0 4.19931E+0 5.788499E+0 0.000000 5.675017E+0 5.644931E+0 3.01795E+0 4.054981E+0 7 177 n-07177 7 178 n-07178 1500.000000 314.000000 100.000000 1.61939E+03 1.605631E+03 8.1456E+0 9.196995E+0 10.000000 3.590087E+0 3.555571E+0 1.88958E+0.9049E+0 7 179 n-07179 7 180 n-07180 956.000000 179.000000 50.000000 1.055950E+03 1.050457E+03 5.7689E+0 6.6740E+0 5.000000.493698E+0.444014E+0 1.03433E+0 1.187488E+0 7 181 n-07181 7 18 n-0718 194.000000 117.000000 31.000000 3.678776E+0 3.645149E+0 1.050146E+0 1.166585E+0 41.000000.4193E+0.389883E+0 6.353631E+01 7.901E+01 73 179 n-073179 73 180 n-073180 1334.000000 1640.000000 4.000000 3.00448E+03.99856E+03 1.50681E+03 1.843845E+03 60.000000 1.896064E+03 1.89068E+03 9.368301E+0 1.9675E+03 73 181 n-073181 73 18 n-07318 766.000000 110.000000 15.000000 9.987947E+0 9.93409E+0 4.807404E+0 6.003485E+0 180.000000 1.16684E+03 1.1636E+03 5.181388E+0 6.0490E+0 74 180 n-074180 74 18 n-07418 536.000000 74.000000 60.000000 9.39716E+0 9.31873E+0 4.545551E+0 6.34833E+0 8.000000 3.895656E+0 3.83650E+0.040834E+0.793579E+0 74 183 n-074183 74 184 n-074184 515.000000 4.000000 15.000000 7.563709E+0 7.517904E+0 3.868400E+0 4.9300E+0 10.000000 3.33056E+0 3.70991E+0 1.46388E+0 1.485116E+0 74 185 n-074185 74 186 n-074186 703.000000 176.000000 113.000000 7.9919E+0 7.9490E+0 3.74810E+0 4.738E+0 5.000000.993088E+0.919654E+0 9.63901E+01 1.146630E+0 75 185 n-075185 75 186 n-075186 1535.000000 1550.000000 6.000000 1.111813E+03 1.107180E+03 6.177715E+0 8.4771E+0 50.000000 1.81379E+03 1.806953E+03 9.45181E+0 1.08854E+03 75 187 n-075187 76 184 n-076184 1160.000000 657.000000 57.000000 9.657551E+0 9.60874E+0 4.94935E+0 5.99890E+0 0.000000 8.96354E+0 8.53446E+0 4.333971E+0 5.540367E+0 76 186 n-076186 76 187 n-076187 4.000000 896.000000 16.000000 5.991306E+0 5.9496E+0 3.05951E+0 3.804084E+0 30.000000 1.101880E+03 1.097844E+03 4.60107E+0 6.31081E+0