Update README.md (072a08a6) · Commits · SCALE / Analysis / 2021 Nuclear Data Assessment for Advanced Reactors

INL-A-MET/README.md

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		@@ -18,19 +18,27 @@ fuel. However, for this project, metal fuel was assumed:

		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.
		>
		> E. Walker, S. Skutnik, W. Wieselquist, A. Shaw, and F. Bostelmann (2021),
		> [2] 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, Oak Ridge National Laboratory, Oak Ridge, TN, 2021.
		> [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

		Input and output files for INL-A-MET 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: Shift
		- Sensitivity analysis: TSUNAMI/IFP
		- Neutron histories: 50,000 x (9,900 + 100)
		- Latent generations: 20
		- Group structure for sensitivity tallies: 302 fast group structure

		```
		INL-A-MET