Merge branch 'add-msre-data' into 'master'

# MSRE

The initial SCALE full core model of the Molten Salt Reactor Experiment (MSRE)

with fresh fuel was developed based on the benchmark specifications for the

MSRE zero-power first critical experiment with U-235 provided in the International

Handbook of Reactor Physics Experiments of the Organisation for Economic Co-operation

and Development (OECD), Nuclear Energy Agency (NEA).

Further models were developed to determine fuel salt compositions for the MSRE

at 375 days which is the number of days that approximately correspond to the

number of hours that the MSRE operated using enriched U-235 fuel. The developed

models consider moving fuel salt through the loop, the removal of noble gases

through the off-gas system, and the plating out of noble metals.

The major references used to develop the provided models are the following:

- D. Shen et al. (2019), _Molten-Salt Reactor Experiment (MSRE) Zero-Power First

  Critical Experiment with U-235,_ MSRE-MSR-EXP-001, International Handbook

  of Reactor Physics Experiments, OECD/NEA.

- M. Fratoni, D. Shen, G. Ilas, and J. Powers (2020), _Molten Salt Reactor Experiment

  Benchmark Evaluation,_ [DOE-UCB-8542](https://www.osti.gov/servlets/purl/1617123), 16-10240, University of California, Berkeley, CA.

- R. C. Robertson, _MSRE design and operations report part I: Description of reactor design,_ ORNL-TM-0728, 1965.

Results obtained with the MSRE full core model developed for the benchmark are 

summarized in the following publication:

> F. Bostelmann, S. E. Skutnik, E. Walker, G. Ilas, and W. A. Wieselquist (2021),

> _Modeling of the Molten Salt Reactor Experiment with SCALE,_ Nuclear Technology,

> doi:[10.1080/00295450.2021.1943122](https://doi.org/10.1080/00295450.2021.1943122)

Methods developed and results obtained for the MSRE at 375 days are

summarized in the following ORNL TM report:

> A. Lo, F. Bostelmann, B. Betzler, D. Hartando, W. A. Wieselquist (2022), _Application of SCALE

> MSR Tools to Molten Salt Fueled Reactor Physics in Support of Severe Accident

> Analyses,_ ORNL/TM-2022/1844, Oak Ridge National Laboratory.

**Please always provide both references when using files and data provided here.**

:warning: The models provided here might differ from the models used for the

studies summarized in the report since models are updated based upon feedback. :warning:

## Content

Multiple SCALE model input and output files are provided:

- full core with fresh fuel salt according to the IRPhEP benchmark definition

    - criticality model (CSAS6-KENO)

    - model with discretized zones in the active region to obtain power profiles (TRITON-KENO)

- full core with fuel salt at 375 days

    - model with discretized zones in the active region to obtain power profiles (TRITON-KENO)

- slice model through the core center for depletion

    - "TRITON-MSR" model to obtain system-average fuel salt compositions (TRITON-KENO with flow block)

    - Consideration of fission gas removal and noble metal plating out

- Slug flow model following slug of fuel through the core and loop

    - ORIGEN model to determine fuel salt composition at different regions in the core and loop

    - Consideration of fission gas removal

The following region labels are used:

- region 1: major core region (moderated region in cylindrical portion of core)

- region 2: upper head of the vessel (upper plenum)

- region 3: pipe between vessel and pump

- region 4: pump

- region 5: pipe between pump and heat exchanger

- region 6: heat exchanger

- region 7: pipe between heat exchanger and core inlet

- region 8: core inlet

- region 9: lower vessel head (lower plenum)

- core: salt in the reactor vessel; the sum of regions 1, 2, 8, and 9

- system: the sum of regions 1 to 9

```

MSRE

├── benchmark_fresh_core

│   ├── msre_discretized.ce_v7.1_endf.t6-depl.inp

│   ├── msre_discretized.ce_v7.1_endf.t6-depl.out

│   ├── msre_simple.ce_v7.1_endf.csas6.fission_density.3dmap

│   ├── msre_simple.ce_v7.1_endf.csas6.flux.3dmap

│   ├── msre_simple.ce_v7.1_endf.csas6.inp

│   └── msre_simple.ce_v7.1_endf.csas6.out

├── flow_loop

│   ├── get_dch_from_flow_loop.sh

│   ├── inventory_files

│   │   ├── msre_core.f71

│   │   ├── msre_core.ii.json

│   │   ├── msre_region*.f71

│   │   ├── msre_region*.ii.json

│   │   ├── msre_system.f71

│   │   └── msre_system.ii.json

│   ├── melcor_files

│   │   ├── msre_core.melcor.dch.inp

│   │   ├── msre_region*.melcor.dch.inp

│   │   └── msre_system.melcor.dch.inp

│   ├── msre_core_decay.ce_v7.1_endf.origen.inp

│   ├── msre_core_decay.ce_v7.1_endf.origen.out

│   ├── msre_loop_*.ce_v7.1_endf.origen.inp

│   ├── msre_loop_*.ce_v7.1_endf.origen.out

│   ├── msre_loop_10.ce_v7.1_endf.origen.f71

│   ├── msre_regions_decay.ce_v7.1_endf.origen.inp

│   ├── msre_regions_decay.ce_v7.1_endf.origen.out

│   ├── msre_system_decay.ce_v7.1_endf.origen.inp

│   └── msre_system_decay.ce_v7.1_endf.origen.out

├── full_core_375days

│   ├── msre_equilibrium.ce_v7.1_endf.t6-depl.inp

│   └── msre_equilibrium.ce_v7.1_endf.t6-depl.out

└── slice

    ├── get_dch_from_slice.sh

    ├── inventory_files

    │   ├── msre_noble_metal_decay.f71

    │   ├── msre_noble_metal_decay.ii.json

    │   ├── msre_off_gas_decay.f71

    │   ├── msre_off_gas_decay.ii.json

    │   ├── msre_system_decay.f71

    │   └── msre_system_decay.ii.json

    ├── melcor_files

    │   ├── msre_noble_metal_decay.melcor.dch.inp

    │   ├── msre_off_gas_decay.melcor.dch.inp

    │   └── msre_system_decay.melcor.dch.inp

    ├── msre_decay.ce_v7.1_endf.origen.inp

    ├── msre_decay.ce_v7.1_endf.origen.out

    ├── msre_slice.ce_v7.1_endf.t6-depl.f71

    ├── msre_slice.ce_v7.1_endf.t6-depl.inp

    ├── msre_slice.ce_v7.1_endf.t6-depl.*.f33

    └── msre_slice.ce_v7.1_endf.t6-depl.out

```

- inp: text input file

- out: text output file

- ii.json: inventory interface JSON file

- f33: ORIGEN binary library file

- f71: ORIGEN binary concentration file

- 3dmap: binary mesh tally file

- sh: shell script

Note that the inventory on the ii.json file is normalized to 1 metric ton initial heavy metal. MELCOR DCH files are adjusted to the actual region heavy metal content.

<!-- ## Related presentations

Analyses related to the this model were presented at a public workshop organized by the NRC.

Information about this meeting can be found [here](URL)

and the meeting slides can be accessed [here](URL). -->