Commit 0983c048 authored by Betzler's avatar Betzler
Browse files

Corrections in README and in input comments for consistency and precision.

parent 652dbd4d

EBR-II/README.md

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@@ -2,7 +2,8 @@ 


## Modeling basis



The SCALE full core model of the EBR-II was developed based on the benchmark specifications provided in the International Handbook of Reactor Physics

The SCALE full core model of the EBR-II was developed based on the benchmark 

specifications provided in the International Handbook of Reactor Physics

Experiments of the Organisation for Economic Co-operation and Development

(OECD), Nuclear Energy Agency (NEA):
@@ -12,13 +13,13 @@ Experiments of the Organisation for Economic Co-operation and Development 


## Model citation



Cite the following references when using this model:

Please cite the following 2 references when using this model:



* F. Bostelmann, G. Ilas, W. Wieselquist (2021), _Nuclear Data Sensitivity

* F. Bostelmann, G. Ilas, W. A. Wieselquist (2021), _Nuclear Data Sensitivity

  Study for the EBR-II Fast Reactor Benchmark Using SCALE with ENDF/B-VII.1

  and ENDF/B-VIII.0,_ Journal of Nuclear Engineering, 2, 345-367,

  doi:[10.3390/jne2040028](https://www.mdpi.com/2673-4362/2/4/28).

* F. Bostelmann, G. Ilas, C. Celik, A. M. Holcomb, and W. Wieselquist (2021),

* F. Bostelmann, G. Ilas, C. Celik, A. M. Holcomb, and W. A. Wieselquist (2021),

  _Nuclear Data Assessment for Advanced Reactors,_

  [NUREG/CR-7289, ORNL/TM-2021/2002](https://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr7289/index.html),

  Oak Ridge National Laboratory, Oak Ridge, TN.
@@ -39,11 +40,10 @@ calculations with the TSUNAMI-Shift sequence are provided. Calculation settings: 
EBR-II

└── benchmark_fresh_core

    ├── ebr2.tsu_ce.ce_v7.1_endf.inp

    ├── ebr2.tsu_ce.ce_v7.1_endf.sdf

    └── ebr2.tsu_ce.ce_v7.1_endf.out

    ├── ebr2.tsu_ce.ce_v7.1_endf.out

    └── ebr2.tsu_ce.ce_v7.1_endf_ifp.sdf

```



* inp: text input file

* out: text output file

* sdf: sensitivity data file

* sdf: k-eff sensitivity data file

EBR-II/benchmark_fresh_core/ebr2.tsu_ce.ce_v7.1_endf.inp

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@@ -2,13 +2,20 @@ 
'+EBR-II full core+

'+================+

'

' Cite usage of model with the following reference:

' F. Bostelmann, G. Ilas, W. Wieselquist (2021). "Nuclear Data Sensitivity

' Please cite the following 2 references when using this model:

'

' [1] F. Bostelmann, G. Ilas, W. A. Wieselquist (2021), "Nuclear Data Sensitivity

' Study for the EBR-II Fast Reactor Benchmark Using SCALE with ENDF/B-VII.1

' and ENDF/B-VIII.0," Journal of Nuclear Engineering, 2, 345-367,

' doi:10.3390/jne2040028, https://www.mdpi.com/2673-4362/2/4/28

' [2] F. Bostelmann, G. Ilas, C. Celik, A. M. Holcomb, and W. A. Wieselquist (2021),

' "Nuclear Data Assessment for Advanced Reactors," NUREG/CR-7289, 

' ORNL/TM-2021/2002, Oak Ridge National Laboratory, Oak Ridge, TN, 

' https://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr7289/index.html

'

'

' Modeling Basis:

'

' Reference:

' International Reactor Physics Experiment Evaluation Project (IRPhEP) Handbook

' Edward S. Lum, et al., "Evaluation of Run 138B at Experimental Breeder Reactor II,

' a Prototype Liquit Metal Fast Breeder Reactor," NEA/NSC/DOC(2006)1, EBR2-LMFR-RESR-001, CRIT

HTR-10/README.md

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@@ -2,7 +2,8 @@ 


## Modeling basis



The SCALE full core model of the HTR-10 was developed based on the benchmark specifications for initial critical experiment at room temperature provided in

The SCALE full core model of the HTR-10 was developed based on the benchmark 

specifications for initial critical experiment at room temperature provided in

the International Handbook of Reactor Physics Experiments of the Organisation

for Economic Co-operation and Development (OECD), Nuclear Energy Agency (NEA):
@@ -15,16 +16,16 @@ A description of the basic design features can be found in 


## Model citation



Cite the following references when using this model:

Please cite the following 2 references when using this model:



* F. Bostelmann, G. Ilas, C. Celik, A. M. Holcomb, and W. Wieselquist (2021),

  _Nuclear Data Assessment for Advanced Reactors,_

  [NUREG/CR-7289, ORNL/TM-2021/2002](https://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr7289/index.html),

  Oak Ridge National Laboratory, Oak Ridge, TN.

* G. Ilas, D. Ilas, R. P. Kelly, E. E. Sunny (2012), _Validation of SCALE

  for High Temperature Gas-Cooled Reactor Analysis,_

  [NUREG/CR-7107, ORNL/TM-2011/161](https://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr7107/index.html),

  Oak Ridge National Laboratory, Oak Ridge, TN.

* F. Bostelmann, G. Ilas, C. Celik, A. M. Holcomb, and W. A. Wieselquist (2021),

  _Nuclear Data Assessment for Advanced Reactors,_

  [NUREG/CR-7289, ORNL/TM-2021/2002](https://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr7289/index.html),

  Oak Ridge National Laboratory, Oak Ridge, TN.



## Content
@@ -42,10 +43,10 @@ calculations with the TSUNAMI-Shift sequence are provided. Calculation settings: 
HTR-10

└── benchmark_fresh_core

    ├── htr10.tsu_ce.ce_v7.1_endf.inp

    ├── htr10.tsu_ce.ce_v7.1_endf.sdf

    └── htr10.tsu_ce.ce_v7.1_endf.out

    ├── htr10.tsu_ce.ce_v7.1_endf.out

    └── htr10.tsu_ce.ce_v7.1_endf_ifp.sdf

```



* inp: text input file

* out: text output file

* sdf: sensitivity data file
 
* sdf: k-eff sensitivity data file

HTR-10/benchmark_fresh_core/htr10.tsu_ce.ce_v7.1_endf.inp

+16 −7
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'=============================================================================

' HTR-10 model for initial criticality



' Please cite usage of this model as:

' G. Ilas, D. Ilas, R. P. Kelly, E. E. Sunny (2012). Validation of SCALE 

' for High Temperature Gas-Cooled Reactor Analysis. NUREG/CR-7107, U.S. 

' Nuclear Regulatory Commission.



' Modeling basis:

'=============================================================================

'

' Please cite the following 2 references when using this model:

'

' [1] G. Ilas, D. Ilas, R. P. Kelly, E. E. Sunny (2012), "Validation of SCALE

' for High Temperature Gas-Cooled Reactor Analysis," NUREG/CR-7107, 

' ORNL/TM-2011/161, Oak Ridge National Laboratory, Oak Ridge, TN.

' https://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr7107/index.html

' [2] F. Bostelmann, G. Ilas, C. Celik, A. M. Holcomb, and W. A. Wieselquist (2021),

' "Nuclear Data Assessment for Advanced Reactors," NUREG/CR-7289, 

' ORNL/TM-2021/2002, Oak Ridge National Laboratory, Oak Ridge, TN, 

' https://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr7289/index.html

'

'

' Modeling Basis:

'

' W. K. Terry, L. M. Montierth, S. S. Kim, J. J. Cogliati, A. M. Ougouag (2007). 

' Evaluation of the initial critical configuration of the HTR-10 pebble-bed reactor.

' HTR10-GCR-RESR-001, NEA/NSC/DOC[2006]1, Rev. 0, OECD/NEA.

INL-A-MET/README.md

+16 −16
Original line number Diff line number Diff line
@@ -8,24 +8,24 @@ Laboratory. The INL Design A concept is an adaptation of the Megapower HPR 
developed by Los Alamos National Laboratory. The original design contains oxide

fuel. However, for this project, metal fuel was assumed:



* J. W. Sterbentz Sterbentz, J. W. Werner, A. J. Hummel, J. C. Kennedy,

  R. C. O. Brien, A. M. Dion, R. N. Wright, K. P. Ananth, Krishnan P (2018),

* J. W. Sterbentz, J. W. Werner, A. J. Hummel, J. C. Kennedy,

  R. C. O. Brien, A. M. Dion, R. N. Wright, K. P. Ananth (2018),

  _Preliminary Assessment of Two Alternative Core Design Concepts for the Special

  Purpose Reactor,_ INL/EXT-17-43212, Rev. 1, Idaho National Laboratory,

  Idaho Falls, ID.

  Purpose Reactor,_ [INL/EXT-17-43212, Rev. 1](https://doi.org/10.2172/1413987), 

  Idaho National Laboratory, Idaho Falls, ID.



## Model citation



Cite the following references when using this model:

Please cite the following 2 references when using this model:



* F. Bostelmann, G. Ilas, C. Celik, A. M. Holcomb, and W. Wieselquist (2021),

* E. D. Walker, S. E. Skutnik, W. A. Wieselquist, A. M. 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.

* F. Bostelmann, G. Ilas, C. Celik, A. M. Holcomb, and W. A. Wieselquist (2021),

  _Nuclear Data Assessment for Advanced Reactors,_

  [NUREG/CR-7289, ORNL/TM-2021/2002](https://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr7289/index.html),

  Oak Ridge National Laboratory, Oak Ridge, TN.

* E. Walker, S. Skutnik, W. 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, 2021.



## Content
@@ -43,10 +43,10 @@ calculations with the TSUNAMI-Shift sequence are provided. Calculation settings: 
INL-A-MET

└── full_core

    ├── hpr_inla_met.tsu_ce.ce_v7.1_endf.inp

    ├── hpr_inla_met.tsu_ce.ce_v7.1_endf.sdf

    └── hpr_inla_met.tsu_ce.ce_v7.1_endf.out

    ├── hpr_inla_met.tsu_ce.ce_v7.1_endf.out

    └── hpr_inla_met.tsu_ce.ce_v7.1_endf_ifp.sdf

```



* inp: text input file

* out: text output file

* sdf: sensitivity data file
 
* sdf: k-eff sensitivity data file