Commit add2fac7 authored by Bostelmann, Rike's avatar Bostelmann, Rike
Browse files

Update README

parent 7dbdc31c
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@@ -24,6 +24,8 @@ studies summarized in the report since models are updated based upon feedback. :

## Content

### File overview

SCALE input and output files for the following models are provided:
* CSAS/KENO full core model at BOEC
* CSAS/KENO full core model at EOEC
@@ -33,17 +35,25 @@ SCALE input and output files for the following models are provided:
.
├── README.md
└── full_core
    ├── ABTR250.ce_v7.1_endf.t6-depl.eoc_core_decay.f71
    ├── ABTR250.ce_v7.1_endf.t6-depl.eoc_core_decay.ii.json
    ├── ABTR250.ce_v7.1_endf.t6-depl.eoc_core_decay.melcor.dch.inp
    ├── ABTR250.ce_v7.1_endf.t6-depl.eoc_core_decay_1mtihm.f71
    ├── ABTR250.ce_v7.1_endf.t6-depl.eoc_core_decay_1mtihm.ii.json
    ├── ABTR250.ce_v7.1_endf.t6-depl.eoc_core_decay_1mtihm.melcor.dch.inp
    ├── ABTR250.ce_v7.1_endf.t6-depl.f71
    ├── ABTR250.ce_v7.1_endf.t6-depl.ii.json
    ├── ABTR250.ce_v7.1_endf.t6-depl.inp
    ├── ABTR250.ce_v7.1_endf.t6-depl.out
    ├── ABTR250.core_decay.ii.json
    ├── ABTR250_BOEC.ce_v7.1_endf.csas6.fissionRate.3dmap
    ├── ABTR250_BOEC.ce_v7.1_endf.csas6.gridFluxes.3dmap
    ├── ABTR250_BOEC.ce_v7.1_endf.csas6.inp
    ├── ABTR250_BOEC.ce_v7.1_endf.csas6.out
    ├── ABTR250_EOEC.ce_v7.1_endf.csas6.inp
    └── ABTR250_EOEC.ce_v7.1_endf.csas6.out
    ├── ABTR250_EOEC.ce_v7.1_endf.csas6.out
    ├── origen_eoc_core_decay.inp
    ├── origen_eoc_core_decay.msg
    └── origen_eoc_core_decay.out
```

- inp: text input file
@@ -53,6 +63,18 @@ SCALE input and output files for the following models are provided:
- f71: ORIGEN binary concentration file
- 3dmap: binary mesh tally file

### 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:

* Core-average inventory normalized to 1 MTIHM
  * [II.JSON file](full_core/ABTR250.ce_v7.1_endf.t6-depl.eoc_core_decay_1mtihm.ii.json)
  * [F71 file](full_core/ABTR250.ce_v7.1_endf.t6-depl.eoc_core_decay_1mtihm.f71)
* Core-average inventory scaled to the actual core mass of 4.0468 MTIHM
  * [II.JSON file](full_core/ABTR250.ce_v7.1_endf.t6-depl.eoc_core_decay.ii.json)
  * [F71 file](full_core/ABTR250.ce_v7.1_endf.t6-depl.eoc_core_decay.f71)


## Related presentations

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

The repository currently contains models for the following advanced
reactor concepts:
### Non-LWR models

SCALE models including input and output files for the following list of non-LWR models are contained in this repository. Analyses based on the developed SCALE models were presented in public workshops organized by the NRC.
Information on these workshops, the presentations, and the final reports can be found under the provided links.

##### Pebble-bed High Temperature Gas-cooled Reactor (HTGR):

- Model: PBMR-400
- Reference report: _S. E. Skutnik and W. A. Wieselquist (2021), Assessment of ORIGEN Reactor Library Development for Pebble-Bed Reactors Based on the PBMR-400 Benchmark, [ORNL/TM-2020/1886](https://info.ornl.gov/sites/publications/Files/Pub150728.pdf), Oak Ridge National Laboratory, Oak Ridge, TN._
- [workshop](https://www.nrc.gov/pmns/mtg?do=details&Code=20210770), [slides](https://adamswebsearch2.nrc.gov/webSearch2/main.jsp?AccessionNumber=ML21200A179), [video](https://youtu.be/I_7GIOeXVtw)

##### Heat Pipe Reactor (HPR):

- Model: INL Design A
- Reference report: _E. Walker, S. E. Skutnik, W. A. Wieselquist, A. Shaw, and F. Bostelmann (2021), SCALE Modeling of the Fast-Spectrum Heat Pipe Reactor, [ORNL/TM-2021/2021](https://www.osti.gov/biblio/1871124-scale-modeling-fast-spectrum-heat-pipe-reactor), Oak Ridge National Laboratory, Oak Ridge, TN._
- [workshop](https://www.nrc.gov/pmns/mtg?do=details&Code=20210696), [slides](https://adamswebsearch2.nrc.gov/webSearch2/main.jsp?AccessionNumber=ML21179C060), [video](https://youtu.be/8pRplj75NMw)

##### Fluoride salt-cooled High temperature reactor (FHR):

- Model: UC Berkeley pebble-bed FHR Mark 1 (PB-FHR-Mk1)
- Reference report: _F. Bostelmann, C. Celik, R. F. Kile, W. Wieselquist (2022), SCALE Analysis of a Fluoride Salt Cooled High Temperature Reactor in Support of Severe Accident Analysis, [ORNL/TM-2021/2273](https://info.ornl.gov/sites/publications/Files/Pub168374.pdf), Oak Ridge National Laboratory, Oak Ridge, TN._
- [workshop](https://www.nrc.gov/pmns/mtg?do=details&Code=20210774), [slides](https://adamswebsearch2.nrc.gov/webSearch2/main.jsp?AccessionNumber=ML21256A231), [video](https://youtu.be/YZDqCka_gm4)

##### Molten Salt fueled Reactor (MSR):

- Model: Molten Salt Reactor Experient (MSRE)
- Reference report: _A. Lo, F. Bostelmann, D. Hartanto, B. Betzler, W. A. Wieselquist (2022), Application of SCALE to Molten Salt Fueled Reactor Physics in Support of Severe Accident Analyses, [ORNL/TM-2022/1844](https://info.ornl.gov/sites/publications/Files/Pub173113.pdf), Oak Ridge National Laboratory, Oak Ridge, TN._
- [workshop](https://www.nrc.gov/pmns/mtg?do=details&Code=20220713), [slides](https://adamswebsearch2.nrc.gov/webSearch2/main.jsp?AccessionNumber=ML22255A214), [video](https://www.youtube.com/watch?v=nHHV528O0p0)

##### Sodium-cooled Fast Reactor (SFR):

- Model: Advanced Burner Test Reactor (ABTR)
- Reference report: _A. Shaw, F. Bostelmann, D. Hartanto, E. Walker, W. Wieselquist (2023), SCALE Modeling of the Sodium-Cooled Fast-Spectrum Advanced Burner Test Reactor, [ORNL/TM-2022/2758](https://www.osti.gov/biblio/1991734), Oak Ridge National Laboratory, Oak Ridge, TN._
- [workshop](https://www.nrc.gov/pmns/mtg?do=details&Code=20220714), [slides](https://adamswebsearch2.nrc.gov/webSearch2/main.jsp?AccessionNumber=ML22262A252), [video](https://youtu.be/pinsryEwqC4)

### Inventory for accident progression

For each of the reactors, inventory for accident progression calculations with MELCOR was generated and is provided in this repository. To consider the most conservative conditions of the individual cores, a core-average or system-average inventory file was generated as follows:
* HTGR and FHR: core-average inventory at the state of equilibrium operation
* HPR: core-average inventory at end-of-life 
* SFR: core-average inventory at the end of an equilibrium cycle
* MSR: system-average inventory (considerin the fuel salt inside the core and the loop) at end-of-life

## Related presentations
For use in MELCOR, the core-average or system-average inventory was decayed for 10 days in order to allow consideration of accurate inventory as a function of time during accident progression. 

Analyses based on the developed SCALE models were presented in public workshops organized by the NRC.
Information on these workshops and the presentations can be found under the following links:
The core-average or system-average inventory as a function of 10 days of decay is provided in the form of an ORIGEN concentration file (F71 file) and as JSON-formatted inventory interface (II.JSON). The README files in the individual sections provide links to the specific files. 

- PBMR-400: [workshop](https://www.nrc.gov/pmns/mtg?do=details&Code=20210770), [slides](https://adamswebsearch2.nrc.gov/webSearch2/main.jsp?AccessionNumber=ML21200A179), [video](https://youtu.be/I_7GIOeXVtw)
- INL Design A: [workshop](https://www.nrc.gov/pmns/mtg?do=details&Code=20210696), [slides](https://adamswebsearch2.nrc.gov/webSearch2/main.jsp?AccessionNumber=ML21179C060), [video](https://youtu.be/8pRplj75NMw)
- PB-FHR-Mk1: [workshop](https://www.nrc.gov/pmns/mtg?do=details&Code=20210774), [slides](https://adamswebsearch2.nrc.gov/webSearch2/main.jsp?AccessionNumber=ML21256A231), [video](https://youtu.be/YZDqCka_gm4)
- MSRE: [workshop](https://www.nrc.gov/pmns/mtg?do=details&Code=20220713), [slides](https://adamswebsearch2.nrc.gov/webSearch2/main.jsp?AccessionNumber=ML22255A214), [video](https://www.youtube.com/watch?v=nHHV528O0p0)
- ABTR: [workshop](https://www.nrc.gov/pmns/mtg?do=details&Code=20220714), [slides](https://adamswebsearch2.nrc.gov/webSearch2/main.jsp?AccessionNumber=ML22262A252), [video](https://youtu.be/pinsryEwqC4)
It is noted that many of the inventory result files were generated with the TRITON reactor physics and depletion sequence. By default, this sequence normalizes the inventory to match 1 metric ton initial heavy metal (MTIHM). For easier use of the inventory files, both the normalized inventory and the inventory scaled to the actual core mass is provided.

## Acknowledgements