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77 changes: 77 additions & 0 deletions docs/source/usage/benchdesc/fng-hcpb.rst
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.. _fnghcpb:

FNG Helium Cooled Pebble Bed (HCPB) Tritium Breeder Module (TBM) Mock-up
------------------------------------------------------------------------

This experiment is part of the SINBAD database (`NEA-1553/71 <hhttps://www.oecd-nea.org/science/wprs/shielding/sinbad/fng_hcpb/fnghcpb-a.htm>`_).
Users will need to show proof of licence and request the required input files to use this
benchamark in JADE.

The purpose of this experiment was to validate transport through a mockup of the Helium
Cooled Pebble Bed (HCPB) blanket concept. This is one of the concepts anticipated for
the ITER test blanket module (TBM) programme and in future fusion power plants. The accurate
prediction of the tritium production, one of the primary functions of the blanket is therefore
very important. The experiment was carried out at the FNG facility, described in :ref:`fngsddr`,
in 2005.

Geometry
^^^^^^^^

The geoemtry of the mockup has external dimensions of 31.0 cm x 29.0 cm x 30.9 cm. The bulk of the
geometry consists of beryllium with two layers symmetric across the central plane consisting of
Li2CO3 containing natural Li. Stacks of 12 pellets of Li2C03 encased in Al were assemebled for measuring
the tritium production rate. At the rear is a steel box filled with Li2CO3.

.. figure:: /img/benchmarks/fng-hcpb.jpg
:width: 500
:align: center

Layout of the FNG-HCPB experiment.

Measured data
^^^^^^^^^^^^^

Activation foils were placed at increasing distance from the source through the centre of the
geometry to measure reaction rates. The tritium production rate was measured at four different
depths a the locations of each of the pellet stacks above and below the central axis.

* **Reaction rates**: 197Au(n,g), 58Ni(n,g), 27Al(n,a), 93Nb(n,2n) at depths of 4.055 cm, 10.355 cm,
16.655 cm and 22.955 cm from the block surface. There is an additional measurement at depth 0 cm
for 93Nb(n,2n).
* **Tritium Activity**: Measured for each of the stacks of 12 pellets as shown in the above Figure. The
tritium specific activity is available in units of Bq/g.

MCNP model
^^^^^^^^^^

A single MCNP geometry is used for calculating the reaction rates and tritium activity. The
most recently developed SDEF source from ENEA has been used and a weight window
is included in the input file.

All modifications necessary to the distributed input file are captured in a patch file.

MCNP tallies
^^^^^^^^^^^^^^

The reaction rates are calculated using the F4 tally in MCNP and can be directly compared to
the experimental data set which are presented per source neutron. Tally n.4 is used in all cases.
The reaction MT numbers are by default assigned using the `convention for IRDFF-II <https://www-nds.iaea.org/IRDFF/IRDFF-II_ACE-LST.pdf>`_.
The raw output from MCNP can be compared directly the reported measured data.

The tritium production is tallied for 6Li and 7Li using the reaction MT number 205 for total
triton production. No energy binning is required. The specific activitiy is then calculated as:

.. math::
Specific \; activity (Bq/g) = (MCNP\_result (RR) \times \lambda (s^{-1}) \times n_{tot})/ mass (g)
where :math:`{\lambda}` is the decay constant, :math:`n_{tot}` is the total neutron production and the
mass is for an individual pellet.

Patch file
^^^^^^^^^^
Coming soon...

.. seealso:: **Related papers and contributions:**

* Batistoni, P., Villari, R., TBM - HCPB Neutronics Experiments: Comparisonand Check Consistency among Results Obtained by the Different Teams Implications for ITER TBM Nuclear Design and Final Assessment, FUS-TEC–MA–NE-R-019, ENEA, Dec. 2006.
* Batistoni, P., Carconi, P., Villari, R., Angelone, M., Pillon, M., Zappa, G., Measurements and Analysis of Tritium Production Rate (TPR) in Ceramic Breeder and of Neutron Flux by Activation Rates in Beryllium in TBM Mock-up, FUS-TEC-MA-NE-R-014, Dec. 2005
80 changes: 80 additions & 0 deletions docs/source/usage/benchdesc/fng-sic.rst
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.. _fngsic:

FNG Silicon Carbide (FNG SiC)
-----------------------------

This experiment is part of the SINBAD database (`NEA-1553/56 <https://www.oecd-nea.org/science/wprs/shielding/sinbad/fng_sic/fngsic-a.htm>`_).
Users will need to show proof of licence and request the required input files to use this
benchamark in JADE.

The purpose of this experiment is to validate Si and C cross sections through irradiation
of a monolithc sintered SiC block placed in front of the FNG source. This is in important
structural material that is being explored for several differnt fusion concepts. The
experiment was carried out at the FNG facility, described in :ref:`fngsddr`, in 2001.

Geometry
^^^^^^^^

The SiC mock-up assembly consisted of a sintered SiC block of dimensions 45.72 cm x
45.72 cm x 71.12 cm located 5.3 cm from the FNG source.

.. figure:: /img/benchmarks/fng-sic.jpg
:width: 500
:align: center

Layout of FNG-SiC experiment. Figure taken from the SINBAD repository.

Measured data
^^^^^^^^^^^^^

Four experimental locations were used through the centre of the mock used to measure reaction
rates and nuclear heating at different depths:

* **Reaction rates**: 197Au(n,g), 58Ni(n,g), 27Al(n,a), 93Nb(n,2n) at depths of 10.41 cm, 25.65 cm
40.89 cm and 56.13 cm from the block surface.
* **Nuclear heating**: Measured using TLDs at depths of 14.99 cm, 30.23 cm, 40.47 cm and 60.71 cm.

.. important::
* There was a lack of reliable data on the concentration of boron in the SiC matrix therefore
it is recommended that **data related to thermal interactions are used in relative comparison
only between codes and cross section libraries**. This includes the nuclear heating measurements
and 197Au(n,g) reaction rate.

MCNP model
^^^^^^^^^^

There are two independent MCNP models in order to caputire the geoemetry of the TLD detectors. In
both cases the the most recently developed SDEF source from ENEA has been used and weight windows
are included in each input file.

Further modifications necessary to the distributed input file are captured in the patch file.

MCNP tallies
^^^^^^^^^^^^^^

The total dose in the TLDs is calculated by summation of the neutron and photon dose. The neutron
dose has an associated sensitivity coefficient that varies as a function of depth. The total dose
is then calculated as:

D\ :sub:`t`\ = D\ :sub:`n`\ * K\ :sub:`n`\ + D\ :sub:`g`\

where K\ :sub:`n`\ is the neutron sensitivity coefficient, D\ :sub:`n`\ the neutron dose and
D\ :sub:`g`\ the photon dose.

Neutron and photon energy deposition are calculated through F6 type tallies. Here, Tally n.16 is
used for the neutron energy deposition and Tally n. 26 for photon energy deposition.

JADE post processes the tally results by multiplying by J/MeV=1.602E-13 and g/kg=1000 to give a direct
comparison to the experimental data given in Gy/source neutron.

Reaction rates were calcualted using an F4 type tally - Tally n.4 is used in all cases. The reaction MT numbers
are by default assigned using the `convention for IRDFF-II <https://www-nds.iaea.org/IRDFF/IRDFF-II_ACE-LST.pdf>`_.
The raw output from MCNP can be compared directly the reported measured data.

Patch file
^^^^^^^^^^
Coming soon...

.. seealso:: **Related papers and contributions:**

* Angelone, M., Batistoni, P., Kodeli, I., Petrizzi, L., Pillon, M., Benchmark analysis of neutronics performances of a SIC block irradiated with 14 MeV neutrons, Fusion Engineering and Design, 63-64, 2002.
47 changes: 27 additions & 20 deletions docs/source/usage/benchmarks.rst
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##################
Default Benchmarks
##################
This section describe more in detail all the default benchmarks
that have been implemented in JADE dividing them between
computational and experimental benchmarks.
This section describes more in detail all the default benchmarks
that have been implemented in JADE, dividing them between
computational and experimental benchmarks. It is strongly recommended
that the user reads this documentation carefully before using a specific
benchmark in JADE.

.. important::
* Not all benchmark inputs and related files can be distributed
toghether with JADE due to licensing reasons. In case the user
provide evidence of licensing rights on specific benchmarks, the
together with JADE due to licensing reasons. In this case, if the user
provides evidence of licensing rights on specific benchmarks, the
JADE team will provide the missing input which, once copied
in the ``<JADE_root>\Benchmark inputs`` folder, allow to correctly run them.
in the ``<JADE_root>\Benchmark inputs`` folder, can be run in JADE. The user
should follow the example of distributed benchmarks for folder and naming
convention.
* For some of the benchmarks, weight windows (WW) have been produced and
necessary for the benchmark run. Unfortunately, these WW are often too
heavy for them to be distributed with Git. These files must be downloaded
separately and inserted in a suitable folder in ``<JADE_root>\Benchmark inputs\VRT``.
necessary for the benchmark run. Unfortunately, these WW files are often too
heavy for them to be distributed with Git. These files must be requested
and inserted in to the same folder as the corresponding input file.
* The benchmarks included in JADE can be also divided between
**transport** benchmarks (usually associated with classical
MCNP) and **activation** benchmarks (usually associated with
**transport** benchmarks and **activation** benchmarks (currently perfromed using
D1S-UNED). It is recommended to run these two benchmarks
categories separately, mostly because they require a different
input in terms of library to be assessed. If transport Benchmarks
expect a single library (e.g. ``31c``), activation one require
input in terms of the library to be assessed. If transport benchmarks
expect a single library (e.g. ``31c``), activation ones require
two: an activation library and a transport one for all zaids that
cannot be activated (e.g. ``99c-31c``).
* In activation benchmarks, the library that is considered the assessed one
is always the activation library (i.e. the first provided). No track
is kept during the post-processing of which was the transport library used
and it is responsability of the user to make sure that comparisons between
activation libraries results are done in a coherent way. That is, the
same transport library should be always used.
and it is responsibility of the user to make sure that comparisons between
activation libraries results are done in a coherent way. That is, **the
same transport library should be always used**.


Overview
========
The following tables summarize the computational and experimental benchmarks
that are included in JADE (I), the ones that are currently under developing (D), and
whishlisted ones (W). A more detailed description of the implemented benchmarks can
be found in the following sections.
The following tables summarise the computational and experimental benchmarks
that are included in JADE **(I)**, the ones that are currently under development
**(D)**, and a future wishlist **(W)**. A more detailed description of the implemented
benchmarks can be found in the following sections.

**COMPUTATIONAL BENCHMARKS:**

Expand Down Expand Up @@ -85,6 +88,10 @@ Experimental Benchmarks

.. include:: benchdesc/fng-w.rst

.. include:: benchdesc/fng-sic.rst

.. include:: benchdesc/fng-hcpb.rst

.. include:: benchdesc/tud-fe.rst

.. include:: benchdesc/tud-fng.rst
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47 changes: 4 additions & 43 deletions docs/source/usage/configuration.rst
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Expand Up @@ -158,7 +158,10 @@ Libraries
:width: 400

This sheet contains the paths of nuclear data library index files for the various codes.

It is the users responsibility to ensure these are configured correctly, and that in
the case of comparisons between codes that the xsdir files are equivalent. For a more
detailed description of these files, refer to the appropriate documentation for each
code

.. warning::
Do not use invalid filename characters (e.g. ``"\"``) in the names assigned to the
Expand All @@ -177,48 +180,6 @@ activation libraries. For each library a sheet needs to be added having as name
suffix used in the xsdir file for the library. Only three columns in the table are mandatory
and these are the **Parent**, **MT** and **Daughter** ones.

.. _runconf:

Benchmark run configuration
===========================

for the *Sphere Leakage* and for the *Sphere SDDR* benchmarks ad-hoc run
configuration file are defined and can be found in the
``<JADE_root>\Configuration\Sphere`` and ``<JADE_root>\Configuration\SphereSDDR``
folders. These are .csv files that control for each element or typical material
the following run parameters:

NPS cut-off
specifies the number of particle histories to be set in the MCNP
STOP card.

CTME cut-off
specifies the total computer time to be set in the MCNP STOP card.

Relative Error cut-off
specifies a precision limit for a tally to be set in the MCNP STOP card.

Density [g/cc]
specifies the density to be considered in the sphere for the
isotope/typical material.

Name
name to be used during post-processing (e.g. Hydrogen or SS316L(N)-IG)

Symbol
element symbol (e.g. H) or material number (e.g. M400). In case of material
number the id must be consistent with the ones indicated in the
``<JADE_root>\Benchmarks inputs\TypicalMaterials`` file.

Z
**[Only for elements]** element number (e.g. 1 for H).

Let Override
If True, the general settings specified in the :ref:`mainconfig` file
for the STOP card are considered to have priority on the specific ones.
If False, the specific parameters are not ovveridden by the general ones.


.. _ppconf:

Computational benchmark post-processing configuration
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