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.. _fnghcpb: | ||
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FNG Helium Cooled Pebble Bed (HCPB) Tritium Breeder Module (TBM) Mock-up | ||
------------------------------------------------------------------------ | ||
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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. | ||
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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. | ||
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Geometry | ||
^^^^^^^^ | ||
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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. | ||
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.. figure:: /img/benchmarks/fng-hcpb.jpg | ||
:width: 500 | ||
:align: center | ||
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Layout of the FNG-HCPB experiment. | ||
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Measured data | ||
^^^^^^^^^^^^^ | ||
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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. | ||
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* **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. | ||
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MCNP model | ||
^^^^^^^^^^ | ||
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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. | ||
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All modifications necessary to the distributed input file are captured in a patch file. | ||
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MCNP tallies | ||
^^^^^^^^^^^^^^ | ||
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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. | ||
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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: | ||
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.. 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. | ||
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Patch file | ||
^^^^^^^^^^ | ||
Coming soon... | ||
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.. seealso:: **Related papers and contributions:** | ||
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* 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 |
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.. _fngsic: | ||
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FNG Silicon Carbide (FNG SiC) | ||
----------------------------- | ||
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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. | ||
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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. | ||
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Geometry | ||
^^^^^^^^ | ||
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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. | ||
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.. figure:: /img/benchmarks/fng-sic.jpg | ||
:width: 500 | ||
:align: center | ||
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Layout of FNG-SiC experiment. Figure taken from the SINBAD repository. | ||
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Measured data | ||
^^^^^^^^^^^^^ | ||
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Four experimental locations were used through the centre of the mock used to measure reaction | ||
rates and nuclear heating at different depths: | ||
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* **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. | ||
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.. 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. | ||
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MCNP model | ||
^^^^^^^^^^ | ||
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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. | ||
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Further modifications necessary to the distributed input file are captured in the patch file. | ||
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MCNP tallies | ||
^^^^^^^^^^^^^^ | ||
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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: | ||
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D\ :sub:`t`\ = D\ :sub:`n`\ * K\ :sub:`n`\ + D\ :sub:`g`\ | ||
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where K\ :sub:`n`\ is the neutron sensitivity coefficient, D\ :sub:`n`\ the neutron dose and | ||
D\ :sub:`g`\ the photon dose. | ||
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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. | ||
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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. | ||
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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. | ||
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Patch file | ||
^^^^^^^^^^ | ||
Coming soon... | ||
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.. seealso:: **Related papers and contributions:** | ||
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* 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. |
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