7.8. [ T-Yield ] section¶
This tally gives information on produced nuclei. Nuclei with both the number of protons and neutrons greater than zero are tallied. No residual nuclei calculated by nuclear data libraries are scored. Note that nuclei produced by neutrons with energies below dmax(2) are scored by setting e-mode>=1.
value |
explanation |
reg, r-z, xyz, tet |
Mesh type. A mesh type subsection is required below this option. |
value |
explanation |
(optional) |
This option defines the volume for each region for |
reg vol |
Volume definition. For details see the [volume] section. |
value |
explanation |
|
Maximum number of columns for volume input echo. |
value |
explanation |
all (default), particle name |
Reaction particle. |
value |
explanation |
reg, x, y, z, r |
x axis value of output data. |
tet |
x axis value of output data, only active with mesh=tet. |
xy, yz, xz, rz |
2-dimensional. |
mass |
Mass number distribution. If the nucleus is specified, isotope distribution is used. |
charge |
Atomic number distribution. Nucleus cannot be specified. |
chart |
Nucleus chart, x:N, y:Z. Nucleus cannot be specified. |
dchain |
For DCHAIN output. This option is not available for mesh=r-z only. For this tally, only one axis parameter is defined in the [t-yield] section. |
value |
explanation |
0, 1 |
With stable nuclei and magic number for chart. |
value |
explanation |
|
Define output file names. This is required by each setting of axis. |
value |
explanation |
(optional, |
Define a file name of the past tally in the restart calculation. Even if several axis parameters were defined, specify only one resfile. |
In the [t-yield] section, projectiles to tally can be specified by part, but the output is the sum of their contributions. To obtain each contribution separately, set multiple [t-yield] sections.
When igamma=3 is set in the [parameters] section, information on isomer production based on the EBITEM model can be obtained by setting axis=chart or axis=dchain in this tally.
value |
explanation |
1, 2 |
1: [1/source] 2: [1/cm^3/source] |
value |
explanation |
(optional, D=1.0) |
Normalization factor. |
value |
explanation |
(optional) |
Change the timing of the score. |
product (default) |
Nuclei produced by nuclear reaction are tallied. |
cutoff |
Nuclei stopped by energy cutoff are tallied. If nuclei are not transported, this is the same as product. |
value |
explanation |
(optional) |
Specify mother nuclei. |
all |
all is the default, same as no definition. |
number of mother nuclei |
When setting the number of mother nuclei, define the mothers in the next line. The number of mother can be set as a negative value, in which case the specified mothers are not included for scoring. |
(next line) |
208Pb Pb Nucleus if specified using mass. Without mass, all nuclei are isotopes of Pb. To specify multiple mother groups, use multiple [t-yield] tallies. |
value |
explanation |
(optional) |
Specify output nuclei. |
all |
all is the default, same as no definition. |
number of nuclei |
When setting number of nuclei, define the nuclei in the next line. |
(next line) |
208Pb Pb Nucleus if specified with mass. Without mass, all nuclei are isotopes of Pb. |
When specifying mother and nucleus , use the format described in Section 4.7 .
value |
explanation |
1 (default), 0, -1 |
Option for treating secondary particles produced by nuclear reaction. In the case of output=product. 1: tally all secondary particles including those generated from elastic scattering. 0: tally secondary particles generated only from inelastic scattering. -1: do not tally any secondary particles if one of the secondary particles is the same as the target nucleus, such as elastic scattering case. If not, tally all secondary particles but subtract the target nucleus. In the case of output=cutoff. 0, 1: do not tally any secondary particles. -1: subtract the target nucleus. When elastic=-1, the yields of target nuclei could be a negative value, but those data are ignored in the eps file, regarded as 0 in the figure. |
value |
explanation |
3000 (default) |
Maximum number of nuclides scored in the case of axis=chart or axis=dchain. 0: score the yield of all nuclides on the nuclear chart, 136 charge numbers * 236 mass numbers * 3 meta stables = 96,288. >0: score the yield of nuclides up to this number, and ignore the rest by outputting a warning message. A smaller mxnuclei results in smaller size of allocated memory and shorter computational time, but larger chance to miss the yields of some important nuclides. |
If output=cutoff is specified, the parameters of part and mother are neglected.
value |
explanation |
(optional) |
Title. |
value |
explanation |
(optional) |
ANGEL parameters. |
value |
explanation |
(optional) |
Special format for ANGEL parameters. |
value |
explanation |
1, 2, 3, 4, 5, 6, 7 |
Options for 2-dimensional plot. |
(optional, D=3) |
value |
explanation |
0 (default), 1, 2, 3, 4, 5 |
When mesh=xyz and axis=xy,yz,xz, region border (1), material name (2), region name (3), and LAT number (4) are plotted using this option. gshow=5 outputs only material colors in pixel style when icntl=8. |
value |
explanation |
0 (default), 1, 2, 3 |
When mesh=reg,tet and axis=xy,yz,xz, region border (1), material name (2), and region name (3) are plotted using this option. A xyz mesh section must be added below this option. |
value |
explanation |
2 (default) |
Option to draw lattice or tetrahedral geometry boundary lines when gshow or rshow is specified. |
0 |
Not drawing. |
1 |
Drawing. Note that the line of voxel phantoms may not be drawn clearly. |
2 |
Not drawing the lines in the same cell. |
3 |
Not drawing the lines in the same material. In this case, the boundary of two adjacent cells filled with the same material is not also drawn, even if not lattice or tetrahedral geometry. When gshow>=3, cell and lattice numbers are now shown. |
value |
explanation |
(optional) |
\(x\) axis title. |
value |
explanation |
(optional) |
\(y\) axis title. |
value |
explanation |
(optional) |
\(z\) axis title. |
value |
explanation |
1 (default) |
This option multiplies the region line resolution by a factor of resol with the gshow or rshow option set to define the line thickness. |
value |
explanation |
0.5 (default) |
The option defines the line thickness. |
value |
explanation |
(optional) |
Coordinate transformation number or definition for r-z or xyz mesh. |
value |
explanation |
(optional) |
Specify materials for scoring. |
all |
all is the default, same as no definition. |
number of materials |
To set number of materials, define the material numbers in the next line. The number of materials can be set as a negative value, in which case the specified materials are not included for scoring. |
(next line) |
2 5 8 Material numbers. |
value |
explanation |
(optional, D=9) |
This option corrects the volume value for each mesh when material is defined by the xyz mesh. 0 means no correction. Value of volmat is the number of scans per one xyz mesh side. |
value |
explanation |
0 (default), 1, 2 |
When epsout=1, results are plotted into eps files.
The eps file is named by replacing the extension with |
value |
explanation |
0 (default), 1 |
Generate Bitmap figure of 2-dimensional tally output.
This file is named by replacing the extension with |
value |
explanation |
0 (default), 1 |
Output the tally results in the xyz mesh in the input format of ParaView.
This file is named by replacing the extension with |
value |
explanation |
0 (default), 1 |
Format of output file for ParaView. 0: ascii, 1: binary. |
value |
explanation |
0 (default), 1, 2 |
When foamout=1, generate a file of outputs, numerical data, with OpenFOAM field data format.
This file is named by replacing the extension with |
value |
explanation |
Number of part (default) |
Specify the number of part shown in the eps file. This parameter limits the number of particles shown in a tally eps file, while it does not limit them in a numerical data file. |
value |
explanation |
(optional, D=-9999) |
Minimum value for the i-th counter. |
value |
explanation |
(optional, D=9999) |
Maximum value for the i-th counter. |
value |
explanation |
(optional, D=-9999) |
Minimum value for the i-th history-counter. This parameter cannot be specified in the batch variance mode, istdev=1. |
value |
explanation |
(optional, D=9999) |
Maximum value for the i-th history-counter. This parameter cannot be specified in the batch variance mode, istdev=1. |
value |
explanation |
(optional, D=-1) |
Threshold value of STD cut off. |
When specifying stdcut, PHITS automatically stop the calculation depending on values of STD, standard deviation. This function is available when stdcut is positive and itall=0,1 is set in [parameters] section. When all relative values of STD of the tally result are larger than 0 and smaller than stdcut at the last of one batch, the calculation is stopped. If stdcut in two or more tally sections is set, all the results of the tally sections have to satisfy the conditions in order for the function to work.
value |
explanation |
D=0 (optional) |
When special > 0, nuclear reactions are repeated more than once to increase statistics. |
value |
explanation |
0, 1, 2 (default), 3 |
Option to replace the results of nuclear reaction events with particle production cross section, activation cross section, data. 0: this option is not available. 1: replace with cross section data in nucleon-induced reactions on \(\alpha\), \(^{14}\mathrm{N}\), and \(^{16}\mathrm{O}\) targets. 2: replace with cross section data in a directory specified by file(27), D=file(1)/XS/yield/, in proton, neutron, deuteron, alpha-induced, and photo-nuclear reactions when using the evaluated nuclear data library without e-mode. 3: replace with cross section data in a directory specified by file(27), D=file(1)/XS/yield/, in proton, neutron, deuteron, alpha-induced, and photo-nuclear reactions when using the evaluated nuclear data library with or without e-mode or nuclear reaction models. |
When coll or reaction events belonging to coll are specified in [counter], the counter value changes before the particle information is tallied. Therefore, to tally the information at the moment the reaction event occurs, specify the counter value after the change.
When specifying the ndata option, PHITS replaces the results of nuclear reaction events with special reaction cross section data, ndata=1, or cross section data in a directory specified by file(27) [1], ndata=2,3. This option helps you obtain more reliable production yields when the yield given by the nuclear reaction models does not reproduce the experimental data well. When a nuclear reaction event occurs in a transport calculation, PHITS replaces a tally yield obtained from the evaluated data or model with the cross section data of the ndata option. This replacement occurs only in the tally that specifies ndata and is independent of the other tallies or the transport calculation. Note that double counting may occur if output=cutoff. For example, if a secondary particle produced by a nuclear reaction model has an energy greater than emin, it will be counted twice, with the contribution of the replacement at the time of the reaction event and the contribution at the time of the energy cutoff after its transport. If you want to avoid double counting of tally yields, please set ctmax(i)=0, (i=1,2,3) and ndata in the [counter] section. See also the [counter] section for this method.
When ndata=1, special reaction cross section data are used for particle yields of the tally in reaction events of neutron- or proton-induced reactions on \(^4\mathrm{He}\), \(^{14}\mathrm{N}\), and \(^{16}\mathrm{O}\) targets. The following nuclear reactions are considered. The tally value is evaluated by excitation functions of these nuclear reactions.
^4He(n,x)^3H ^14N(n,x)^3H ^14N(n,x)^7Be ^14N(n,x)^11Be
^14N(n,x)^10C ^14N(n,x)^11C ^14N(n,x)^14C ^14N(n,x)^13N
^16O(n,x)^3H ^16O(n,x)^7Be ^16O(n,x)^11Be ^16O(n,x)^10C
^16O(n,x)^11C ^16O(n,x)^14C ^16O(n,x)^15C ^16O(n,x)^13N
^16O(n,x)^16N ^16O(n,x)^14O ^16O(n,x)^15O ^4He(p,x)^3H
^14N(p,x)^7Be ^14N(p,x)^11Be ^14N(p,x)^10C ^14N(p,x)^11C
^14N(p,x)^13N ^14N(p,x)^14O ^16O(p,x)^3H ^16O(p,x)^7Be
^16O(p,x)^11Be ^16O(p,x)^10C ^16O(p,x)^11C ^16O(p,x)^14C
^16O(p,x)^13N ^16O(p,x)^14O ^16O(p,x)^15O
When ndata=2,3, this option uses cross section data in the directory specified by file(27). From ver. 3.35, activation cross section data of JENDL-5 are stored. You can obtain particle production yields based on JENDL-5 for proton, neutron, deuteron, alpha-induced, and photo-nuclear reactions with energies up to 200, 200, 100, 50, and 200 MeV/n, respectively. If ndata=2, replacement is only performed when using the evaluated nuclear data library without e-mode. If ndata=3, there is no such limitation as above, and PHITS basically replaces the calculated results of all nuclear reaction events. No replacement is made for reactions other than the target nuclides and incident energies given in file(27), and the results of the evaluated nuclear data and nuclear reaction models are tallied as they are.
For ndata=2,3 the production of all particles is evaluated by replacing the cross section data for output=product, but for output=cutoff the production of light ions such as \(d\), \(t\), \(^3\mathrm{He}\), and \(\alpha\) are not replaced. This is because these particles are likely to be produced with energies greater than emin in the calculation of the evaluated nuclear data and nuclear reaction models, and will be tallied at the energy cutoff after transport. However, even with output=cutoff, if the calculation is performed by evaluated nuclear data without e-mode, the production of light ions will not occur, with lionprd=-1 by default, thus replacing all particle production. When ndata=2,3 and axis=dchain, no cross section data replacement is performed for neutron-induced reactions below 20 MeV, because this axis assumes that the production yield from the reactions is calculated using DCHAIN.
For ndata=2,3, you can use original data by changing the data file in file(27), (D=file(1)/dchain-sp/data/).
Its file name should be given as [element symbol]+[mass number(three digits)]+[-y-]+[incident particle ID]+[.dat], for example O_016-y-n.dat or Pd107-y-n.dat.
Here, the incident particle IDs for proton, neutron, deuteron, \(\alpha\), and photon-induced reactions are p, n, d, a, and g, respectively.
Note that if the element has only one character in its symbol, an underline _ must be added after the element symbol.
An example of the production cross section data is as follows.
# ZAP = 48113 LIP = 1 INT = 2
# Elab (MeV) sigma (b)
1.000000e-11 0.000000e+00
2.530000e-08 0.000000e+00
2.000000e+01 0.000000e+00
2.100000e+01 0.000000e+00
...
where ZAP, LIP, and INT are produced nuclei, its isomer state, and interpolation method, respectively. The produced nuclei are specified as \(1000Z+A\), where \(Z\) is atomic number and \(A\), three digits, is mass number. The isomer state is specified by LIP: =0, the ground state; =1, the first metastable state; =2, the second metastable state. The interpolation method INT = (1,2,3,4,5) are as follows.
INT = 1 : Histogram
2 : Linear(x) - Linear(y)
3 : Log(x) - Linear(y)
4 : Linear(x) - Log(y)
5 : Log(x) - Log(y)
The second line should be written as follows.
# Elab (MeV) sigma (b)
The incident energy [MeV] and cross section [barn] should be written in the first and second columns from the third line. The number of the energy bin is not limited. Note that when the incident energy falls outside the energy range specified by the data, the cross section data at the minimum or maximum energies are used, respectively, for the lower and higher energies. Larger nuclei than He are tallied from the data. $, !, and % can be used as comment remarks.