@@ -67,7 +67,7 @@ SCALE input and output files for the following models are provided:
### Inventory for accident progression
The inventory used for accident progression analyses is the core-average end of equilibrium cycle inventory (EOEC) that was calculated using a TRITON full core depletion calculation from beginning of equilibrium cycle (BOEC) to EOEC. TRITON provides inventory for each of the depleted fuel mixture as well as for the weighted sum of these fuel mixtures (i.e., a core-average of all fuel mixtures). This core-average was decayed with ORIGEN for 10 days. The inventory files of interest are the following:
The inventory used for accident progression analyses is the core-average end of equilibrium cycle inventory (EOEC) that was calculated using a TRITON full core depletion calculation from beginning of equilibrium cycle (BOEC) to EOEC. TRITON provides inventory for each of the depleted fuel mixture as well as for the weighted sum of these fuel mixtures (i.e., a core-average of all fuel mixtures). This core-average inventory at EOEC was decayed with ORIGEN for 10 days. The inventory files of interest are the following:
@@ -61,14 +64,14 @@ SCALE model input and output files are provided for two levels of modeling:
### Inventory for accident progression
The inventory used for accident progression analyses is the core-average end of life (EOL) that was calculated using a TRITON full core depletion calculation from beginning of life (BOL) to EOL. TRITON provides inventory for each of the depleted fuel mixture as well as for the weighted sum of these fuel mixtures (i.e., a core-average of all fuel mixtures). This core-average was decayed with ORIGEN for 10 days. The inventory files of interest are the following:
The inventory used for accident progression analyses is the core-average at end of life (EOL) that was calculated using a TRITON full core depletion calculation from beginning of life (BOL) to EOL. TRITON provides inventory for each of the depleted fuel mixture as well as for the weighted sum of these fuel mixtures (i.e., a core-average of all fuel mixtures). This core-average inventory at EOL was decayed with ORIGEN for 10 days. The inventory files of interest are the following:
@@ -49,6 +49,8 @@ studies summarized in the report since models are updated based upon feedback. :
## Content
### Models
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)
@@ -76,8 +78,11 @@ The following region labels are used:
- system: the sum of regions 1 to 9
### File overview
```
MSRE
.
├── README.md
├── benchmark_fresh_core
│ ├── msre_discretized.ce_v7.1_endf.t6-depl.inp
│ ├── msre_discretized.ce_v7.1_endf.t6-depl.out
@@ -102,7 +107,6 @@ MSRE
│ ├── 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
@@ -127,8 +131,9 @@ MSRE
├── 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
├── msre_slice.ce_v7.1_endf.t6-depl.mix*.f33
├── msre_slice.ce_v7.1_endf.t6-depl.out
└── msre_slice.ce_v7.1_endf.t6-depl.system.f33
```
- inp: text input file
@@ -139,11 +144,35 @@ MSRE
- 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.
### Inventory for accident progression
The inventory used for accident progression analyses is the system-average at end of life (EOL) that was calculated using a TRITON depletion calculation of an axial slice through the core (a surrogate model) from beginning of life (BOL) to EOL. For the MSRE, EOL is referring to the operation of 375 equivalent full power days using U-235 enriched fuel. The term "system-average" refers to the fact that the fuel salt is distributed between the reactor core and the various regions in the loop. The TRITON calculation considered the removal of noble gases through the off-gas system (OGS). and the subsequent removal steps to the charcoal bed. This allowed the prediction of an inventory based on the noble gas removal and their decay in the OGS. Additionally, the plating out of noble metals on structural components was considered as well as their decay, and this inventory was tracked individually. These three inventories were decayed with ORIGEN for 10 days. The inventory files of interest are the following:
**Normalized to the a system fuel salt mass of 1 MTIHM:**
The files from the ORIGEN flow loop calculations can be used to obtain region-specific inventory at EOL. However, it was found that densities of only very short-lived fission products vary noticeable between the different regions. Therefore, the system-average fuel salt inventory was deemed appropriate for accident progression analyses.
## 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). -->
Information about this meeting can be found [here](https://www.nrc.gov/pmns/mtg?do=details&Code=20220713)
and the meeting slides can be accessed [here](https://adamswebsearch2.nrc.gov/webSearch2/main.jsp?AccessionNumber=ML22255A214).
