Update README.md

as well other other material compositions and temperatures were taken from the

following references:

- C. Andreades et al. (2014), _Technical Description of the "Mark 1" Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor (PB-FHR) Power Plant_, [UCBTH-14-002](<https://web.mit.edu/nse/pdf/researchstaff/forsberg/FHR Point Design 14-002 UCB.pdf>), Berkeley, CA.

- A. T. Cisneros (2013), _Pebble Bed Reactors Design Optimization Methods and their Application to the Pebble Bed Fluoride Salt Cooled High Temperature Reactor (PB-FHR)_, [Dissertation](https://escholarship.org/uc/item/98384265), University of California, Berkeley, CA.

> [1] C. Andreades et al. (2014), _Technical Description of the "Mark 1" Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor (PB-FHR) Power Plant_, [UCBTH-14-002](<https://web.mit.edu/nse/pdf/researchstaff/forsberg/FHR Point Design 14-002 UCB.pdf>), Berkeley, CA.

>

> [2] A. T. Cisneros (2013), _Pebble Bed Reactors Design Optimization Methods and their Application to the Pebble Bed Fluoride Salt Cooled High Temperature Reactor (PB-FHR)_, [Dissertation](https://escholarship.org/uc/item/98384265), University of California, Berkeley, CA.

## Model citation

Cite the following references when using this model:

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

> [1] 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.

>

> F. Bostelmann, C. Celik, R. F. Kile, W. A. Wieselquist, _SCALE Analysis of a

> [2] F. Bostelmann, C. Celik, R. F. Kile, W. A. Wieselquist, _SCALE Analysis of a

> Fluoride Salt Cooled High Temperature Reactor in Support of Severe Accident Analysis_,

> ORNL/TM-2021/2273, Oak Ridge National Laboratory, Oak Ridge, TN, 2021.

## Content

Input and output files for PB-FHR-Mk1 full core sensitivity and uncertainty

calculations with the TSUNAMI-Shift sequence are provided.

calculations with the TSUNAMI-Shift sequence are provided. Calculation settings:

- SCALE version: 6.3.0

- Neutron transport: KENO-VI

- Sensitivity analysis: TSUNAMI/CLUTCH (with an F* grid)

- Neutron histories: 50,000 x (9,900 + 100)

- Latent generations: 20

- Group structure for sensitivity tallies: 252 group structure

: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: