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6 changes: 3 additions & 3 deletions doc/content/examples/fuel_cycle/index.md
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# Fuel Cycle

This demonstration re-creates the tritium fuel cycle model described by [!cite](Abdou2021).
This demonstration re-creates the tritium fuel cycle model described by [!cite](Abdou2021).

### Generating the Input File

Expand Down Expand Up @@ -144,8 +144,8 @@ lines are model results.

### Python-based Interactive Script

A python-based graphical interactive script is available at [/test/tests/fuel_cycle/fuel_cycle_gui.py](/scripts/fuel_cycle_gui.py) as a demonstration of the various effects of
individual parameters. To use it, navigate to the scripts directory and run the script. All of the input parameters for the model can be changed by editing the associated entry,
A python-based graphical interactive script is available at [/test/tests/fuel_cycle/fuel_cycle_gui.py](/scripts/fuel_cycle_gui.py) as a demonstration of the various effects of
individual parameters. To use it, navigate to the scripts directory and run the script. All of the input parameters for the model can be changed by editing the associated entry,
then clicking the "Run" button. Once the simulation has run, checkboxes will appear for each system-level tritium inventory. Time units can also be adjusted by selecting the appropriate
timescale.

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2 changes: 1 addition & 1 deletion doc/content/verification_and_validation/val-2a.md
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Expand Up @@ -50,7 +50,7 @@ J = 2 A K_r C^2.

## Case and Model Parameters

The beam flux on the upstream side of the sample during the experiment is presented in [val-2a_flux_and_pressure_TMAP4], and only 75 % of the flux remain in the sample. Other case and model parameters used in TMAP8 are listed in [val-2a_set_up_values_TMAP4].
The beam flux on the upstream side of the sample during the experiment is presented in [val-2a_flux_and_pressure_TMAP4], and only 75 % of the flux remains in the sample. Other case and model parameters used in TMAP8 are listed in [val-2a_set_up_values_TMAP4].

!table id=val-2a_flux_and_pressure_TMAP4 caption=Values of beam flux on the upstream side of the sample during the experiment [!citep](anderl1985tritium,longhurst1992verification).
| time (s) | Beam flux $F$ (atom/m$^2$/s) |
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19 changes: 12 additions & 7 deletions doc/content/verification_and_validation/val-2b.md
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This validation problem is taken from [!cite](macaulay1991deuterium) and is part of the validation suite of TMAP4 and TMAP7 [!citep](longhurst1992verification,ambrosek2008verification), which we reproduce here, with some updates.

R.G. Macaulay-Newcombe et al. conducted thermal absorption and desorption experiments, as well as implantation experiments, on wafers of polished beryllium.
Of the several data sets presented, the one modeled here is run 2a1 represented in Figure 2(a) in their publication. The beryllium sample was 0.4 mm thick and had an area of 104 mm$^2$, as illustrated in [val-2b_schematic].
R.G. Macaulay-Newcombe et al. conducted thermal absorption and desorption experiments, as well as implantation experiments, on wafers of polished beryllium [!citep](macaulay1991deuterium).
Of the several data sets presented, the one modeled here is titled "run 2a1" and is represented in Figure 2(a) in their publication [!citep](macaulay1991deuterium). The beryllium sample was 0.4 mm thick and had an area of 104 mm$^2$, as illustrated in [val-2b_schematic].
It was polished to a mirror finish and then exposed to 13.3 kPa of deuterium at 773 K for 50 hours. It was quickly cooled under a vacuum of about 1 $\mu$Pa. The cooling time constant for the apparatus is taken as 45 minutes, which is consistent with the assumption made in [!citep](longhurst1992verification,ambrosek2008verification).
After removing the sample from the charging furnace, it was transferred in the air to a thermal desorption furnace where the temperature was increased from ambient (300 K) to 1073 K at the rate of 3 K/min. This was done under vacuum, and the pressure of the chamber was monitored by the residual gas analysis and calibrated against standard leaks.
In that way, the emission rate from the sample could be measured as a function of temperature. The sample pressure and temperature histories are shown in [val-2b_temperature_pressure_history].
Expand All @@ -25,17 +25,22 @@ Experimental data from that measurement, given in Figure 2 (a) in [!cite](macaul
caption=Pressure and temperature histories.

!alert note title=Uncertainty about cooldown duration.
The exact duration of the cooldown period and its temperature history are uncertain. [!cite](macaulay1991deuterium) provides information about 24 hour-cooldown cycles, but it is unclear whether this applies to the charging chamber alone or to the sample as well. In parallel, [!citep](longhurst1992verification,ambrosek2008verification) assumes that the cooldown lasted for 40 minutes. With an assumed cooling time constant for the apparatus of 45 minutes, this did not enable the sample to cool down to the starting temperature of the desorption phase of the experiment (i.e., 300 K). To model this case in TMAP8, we decided to select a cooldown duration that is long enough to bring the temperature of the sample to around 300 K, but did not unnecessarily increase the length of the history since no significant changes happen to the deuterium distribution at 300 K due to slow kinetics. For these reasons, we selected a cooldown duration of 5 hours, as shown in [val-2b_temperature_pressure_history].
The exact duration of the cooldown period and its temperature history are uncertain. [!cite](macaulay1991deuterium) provides information about 24 hour-cooldown cycles, but it is unclear whether this applies to the charging chamber alone or to the sample as well. In parallel, [!citep](longhurst1992verification,ambrosek2008verification) assume that the cooldown lasted for 40 minutes. With an assumed cooling time constant for the apparatus of 45 minutes, this did not enable the sample to cool down to the starting temperature of the desorption phase of the experiment (i.e., 300 K). To model this case in TMAP8, we decided to select a cooldown duration that is long enough to bring the temperature of the sample to around 300 K, but did not unnecessarily increase the length of the history since no significant changes happen to the deuterium distribution at 300 K due to slow kinetics. For these reasons, we selected a cooldown duration of 5 hours, as shown in [val-2b_temperature_pressure_history].

From Rutherford backscattering measurements made on the samples before charging with deuterium, they deduced that the thickness of the oxide film was 18 nm. This is typical for polished beryllium. The metal is so reactive in air that the film forms almost immediately after any surface oxide removal. On the other hand, it is relatively stable and would only grow slightly when exposed to air between charging and thermal desorption.

This experiment is modeled using a two-segment model in TMAP8 with the segments linked. The first segment is the BeO film which is modeled using 18 elements, each 1 nm in length. The second segment is the beryllium with reflective boundary condition at the mid-plane. The beryllium segment is modeled using 40 elements, each 50 $\mu$m thick. The solubility of deuterium in beryllium used was that given by [!cite](wilson1990beryllium) at Sandia National Laboratory (SNL) based on the work done by W. A. Swansiger, also of SNL.

The diffusivity of deuterium in beryllium was measured by [!cite](abramov1990deuterium). They made measurements on high-grade (99$\%$ pure) and extra-grade (99.8$\%$ pure). The values used here are those for high-grade beryllium, consistent with Dr. Macaulay-Newcombe's measurements of the purity of his samples.

Deuterium transport properties of the BeO are more challenging. First, it is not clear in which state the deuterium exists in the BeO. However, it has been observed [!cite](longhurst1990tritium) that an activation energy of -78 kJ/mol (exothermic reaction) is evident for tritium coming out of neutron-irradiated beryllium in work done by D. L. Baldwin of Pacific Northwest Laboratory. The same value of energy has appeared in other results (can be inferred from Dr. Swansiger's work cited by [!cite](wilson1990beryllium) and by [!cite](causey1990tritium), among others), so one may be justified in using it. Concerning the solubility, measurements reported by [!cite](macaulay1992thermal) and in follow-up conversations indicate about 200 appm of D in BeO after exposure to 13.3 kPa of D$_2$ at 773 K. That suggests a coefficient of only 1.88 $\times$ 10$^{18}$ d/m$^3$Pa$^{1/2}$. Since much of the deuterium in the oxide layer will get out during the cool-down process (and because it gives a good fit), the solubility coefficient is taken to be 5 $\times$ 10$^{20}$ d/m$^3$Pa$^{1/2}$.
Deuterium transport properties of the BeO are more challenging. First, it is not clear in which state the deuterium exists in the BeO.
However, it has been observed [!cite](longhurst1990tritium) that an activation energy of -78 kJ/mol (exothermic solution) is evident for tritium coming out of neutron-irradiated beryllium in work done by D. L. Baldwin of Pacific Northwest Laboratory.
The same value of energy has appeared in other results. It can be inferred from Dr. Swansiger's work cited by [!cite](wilson1990beryllium) and by [!cite](causey1990tritium), among others, so one may be justified in using it.
Concerning the solubility, measurements reported by [!cite](macaulay1992thermal) and in follow-up conversations indicate about 200 appm of D in BeO after exposure to 13.3 kPa of D$_2$ at 773 K.
That suggests a coefficient of only 1.88 $\times$ 10$^{18}$ d/m$^3$Pa$^{1/2}$.
Since much of the deuterium in the oxide layer will get out during the cool-down process (and because it gives a good fit), the solubility coefficient is taken to be 5 $\times$ 10$^{20}$ d/m$^3$Pa$^{1/2}$.

Deuterium diffusion measurements in BeO were made by [!cite](fowler1977tritium). They found a wide range of results for diffusivity in BeO depending on the physical form of the material, having measured it for single-crystal, sintered, and powdered BeO. The model in [!citep](longhurst1992verification,ambrosek2008verification) uses one expression for the charging phase and another for the thermal desorption phase, believing that the surface film changed somewhat during the transfer between the two furnaces. For the charging phase diffusivity, the model uses 20 times that for the sintered BeO. Thermal expansion mismatches tend to open up cracks and channels in the oxide layer, so this seems a reasonable value. The same activation energy of 48.5 kJ/mol, is retained, however. For the thermal desorption phase, the diffusivity prefactor of the sintered material (7x10$^{-5}$ m$^2$/sec) and an activation energy of 223.7 kJ/mol (53.45 kcal/mol) are used. These values give good results and lie well within the scatter of Fowler's data. Exposure of the sample to air after heating should have made the oxide more like a single crystal by healing the cracks that may have developed. Diffusivities and solubilities used in the simulation are listed in [val-2b_parameters].
Deuterium diffusion measurements in BeO were made by [!cite](fowler1977tritium). They found a wide range of results for diffusivity in BeO depending on the physical form of the material, having measured it for single-crystal, sintered, and powdered BeO. The model in [!citep](longhurst1992verification,ambrosek2008verification) uses one expression for the charging phase and another for the thermal desorption phase, believing that the surface film changed somewhat during the transfer between the two furnaces. For the charging phase diffusivity, the model uses 20 times that for the sintered BeO. Thermal expansion mismatches tend to open up cracks and channels in the oxide layer, so this seems a reasonable value. The same activation energy of 48.5 kJ/mol, is retained, however. For the thermal desorption phase, the diffusivity prefactor of the sintered material (7x10$^{-5}$ m$^2$/sec) and an activation energy of 223.7 kJ/mol (53.45 kcal/mol) are used. These values give results lying well within the scatter of Fowler's data. Exposure of the sample to air after heating should have made the oxide more like a single crystal by healing the cracks that may have developed. Diffusivities and solubilities used in the simulation are listed in [val-2b_parameters].

!table id=val-2b_parameters caption=Model parameter values for the charging and the desorption phases [!citep](longhurst1992verification,ambrosek2008verification). $T$ is the temperature in Kelvin.
| Property of deuterium | Value for charging phase | Value for desorption phase | Units |
Expand All @@ -45,7 +50,7 @@ Deuterium diffusion measurements in BeO were made by [!cite](fowler1977tritium).
| Solubility in Be | $7.156 \times 10^{27} \exp(-11606/T)$ | $7.156 \times 10^{27} \exp(-11606/T)$ | at/m$^3$/Pa$^{1/2}$ |
| Solubility in BeO | $5.00 \times 10^{20} \exp(9377.7/T)$ | $5.00 \times 10^{20} \exp(9377.7/T)$ | at/m$^3$/Pa$^{1/2}$ |

The model applies 13.3 kPa of D$_2$ for 50 hours and 15 seconds followed by cool down with a 45 minute time constant at 1 $\mu$Pa for five hour ([!cite](longhurst1992verification,ambrosek2008verification) used 40 minutes, but we extend it here to 5 hours to let the temperature go down closer to 300 K - see [val-2b_temperature_pressure_history]). The deuterium concentrations in the sample have a complex distribution that results from first charging the sample and then discharging it during the cool down. This problem is then restarted with different model parameters (see [val-2b_parameters]) to simulate thermal desorption in a $1 \times 10^{-3}$ Pa environment. That begins at 300 K and goes to 1073 K at 3 K/min.
The model applies 13.3 kPa of D$_2$ for 50 hours and 15 seconds followed by cool down with a 45 minute time constant at 1 $\mu$Pa for five hour ([!cite](longhurst1992verification,ambrosek2008verification) used 40 minutes, but we extend it here to 5 hours to let the temperature go down closer to 300 K - see [val-2b_temperature_pressure_history]). The deuterium concentrations in the sample have a complex distribution that results from first charging the sample and then discharging it during the cool down. This problem is then restarted with different model parameters (see [val-2b_parameters]) to simulate thermal desorption in a $1 \times 10^{-3}$ Pa environment that begins at 300 K and goes to 1073 K at 3 K/min.

## Results

Expand All @@ -58,7 +63,7 @@ The model applies 13.3 kPa of D$_2$ for 50 hours and 15 seconds followed by cool
caption=Comparison of TMAP8 calculation against experimental data, which shows TMAP8's ability to accurately model this validation case.

!alert note title=Experimental data from [!cite](macaulay1991deuterium).
The experimental data used in this case comes directly from Figure (2) in [!cite](macaulay1991deuterium). This is in contrast with the data used in [!cite](longhurst1992verification,ambrosek2008verification), which, although the scale of the data is very similar, differs slightly. Note also that the units in Figure (2) from [!cite](macaulay1991deuterium) should be atoms/mm$^2$/s $\times 10^{10}$ instead of atoms/mm$^2$ $\times 10^{10}$, which is corrected in [val-2b_comparison].
The experimental data used in this case comes directly from Figure (2) in [!cite](macaulay1991deuterium). This is in contrast with the data used in [!cite](longhurst1992verification,ambrosek2008verification), which, although the scale of the data is very similar, differ slightly. Also, note that the units in Figure (2) from [!cite](macaulay1991deuterium) should be atoms/mm$^2$/s $\times 10^{10}$ instead of atoms/mm$^2$ $\times 10^{10}$, which is corrected in [val-2b_comparison].

To verify that the solubility ratio at the interface between the beryllium and its oxide is appropriately modeled, [val-2b_ratio] compares the known solubility ratio with the calculated deuterium concentration ratio at the interface, and they match, as expected.

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9 changes: 4 additions & 5 deletions doc/content/verification_and_validation/val-2c.md
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Expand Up @@ -9,9 +9,8 @@ Whenever tritium is released into a fusion reactor test cell, it is crucial to c
This case models an experiment conducted at Los Alamos National Laboratory at the tritium systems test assembly (TSTA) to study the behavior of tritium once released in a test cell and the efficacy of the emergency tritium cleanup system (ETCS).

The experimental set up, described in greater detail in [!cite](Holland1986), can be summarized as such:
the inner walls of an enclosure of volume $V$ was covered with an aluminum foil and then covered in paint with an average thickness $l$, which is then in contact with the enclosure air.
A given amount, T$_2^0$, of tritium, T$_2$, is injected in the enclosure, which initially contained ambient air.
This represents the tritium release.
the inner walls of an enclosure of volume $V$ are covered with an aluminum foil and then covered in paint with an average thickness $l$, which is then in contact with the enclosure air.
A given amount, T$_2^0$, of tritium, T$_2$, is injected in the enclosure, which initially contained ambient air, representing tritium release.
A flow rate $f$ through the enclosure represents the air replacement time expected for large test cells.
The purge gas is ambient air with 20% relative humidity.
A fraction of that amount is diverted through the measurement system to determine the concentrations of chemical species within the enclosure.
Expand All @@ -36,15 +35,15 @@ Here, $c_i$ represents the concentration of species $i$, and $K^0$ is a constant

Second, the different species will permeate in the paint.
The elemental tritium species, T$_2$ and HT, have a given solubility $K_S^e$ and diffusivity $D^e$, while the tritiated water, HTO, and water, H$_2$O, have a solubility $K_S^w$ and diffusivity $D^w$.
It is expected that species will initially permeate into the paint and later get released as the purge gas cleans up the enclosure air.
It is expected that the species will initially permeate into the paint and later get released as the purge gas cleans up the enclosure air.

The objectives of this case are to determine the time evolution of T$_2$ and HTO concentrations in the enclosure, match the experimental data published in [!cite](Holland1986), and display this comparison with the appropriate error checking (see [val-2c_comparison_T2] and [val-2c_comparison_HTO]).

## Model Description

To model the case described above, TMAP8 simulates a one-dimensional domain with one block to represent the air in the enclosure, and another block to represent the paint.
In each block, the simulation tracks the local concentration of T$_2$, HT, HTO, and H$_2$O.
Note that this case can easily be extended to a two- or three-dimensional case, but, consistent with previous analyses, we will maintain the one-dimensional configuration here.
Note that this case can easily be extended to a two- or three-dimensional case, but consistent with previous analyses, we will maintain the one-dimensional configuration here.

In the enclosure, to capture the purge gas and the chemical reactions, the concentrations evolve as
\begin{equation} \label{eq:enclosure:T2}
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