Update READMEs (53c4c018) · Commits · SCALE / Analysis / 2021 Nuclear Data Assessment for Advanced Reactors

EBR-II/README.md

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		# EBR-II

		## 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
		Experiments of the Organisation for Economic Co-operation and Development
		(OECD), Nuclear Energy Agency (NEA):
		@@ -8,6 +10,8 @@ Experiments of the Organisation for Economic Co-operation and Development
		> _Evaluation of Run 138B at Experimental Breeder Reactor II, a prototypic
		> liquid metal reactor,_ EBR2-LMFR-RESR-001, NEA/NSC/DOC[2006]1, Rev. 0, OECD/NEA.

		## Model citation

		Cite the following references when using this model:

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

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		# HTR-10

		## 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 International Handbook of Reactor Physics Experiments of the Organisation
		for Economic Co-operation and Development (OECD), Nuclear Energy Agency (NEA):
		@@ -11,6 +13,8 @@ for Economic Co-operation and Development (OECD), Nuclear Energy Agency (NEA):
		A description of the basic design features can be found in
		[NUREG/CR-7107](https://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr7107/index.html).

		## Model citation

		Cite the following references when using this model:

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

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		# INL-A-MET

		## Modeling basis

		The SCALE models provided here are based on the preconceptual design for a
		small, modular 5 MWth heat pipe-cooled reactor (HPR) proposed by Idaho National
		Laboratory. The INL Design A concept is an adaptation of the Megapower HPR
		@@ -12,6 +14,8 @@ fuel. However, for this project, metal fuel was assumed:
		> Purpose Reactor,_ INL/EXT-17-43212, Rev. 1, Idaho National Laboratory,
		> Idaho Falls, ID.

		## Model citation

		Cite the following references when using this model:

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

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		# MET1000

		## Modeling basis

		The MET1000 (or ABR1000) reactor model was developed based on the specifications
		of an OECD/NEA benchmark:

		@@ -7,6 +9,8 @@ of an OECD/NEA benchmark:
		> for Design, Operation and Safety Analysis of SFRs, Core definitions, Version 1.6,_
		> OECD/NEA.

		## Model citation

		Cite the following references when using this model:

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

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		# MSRE

		## Modeling basis

		The SCALE full core model of the Molten Salt Reactor Experiment (MSRE)
		with fresh fuel was developed based on the benchmark specifications for the
		MSRE zero-power first critical experiment with U-235 provided in the International
		@@ -17,6 +19,8 @@ The major references used to develop the provided models are the following:
		>
		> R. C. Robertson, _MSRE design and operations report part I: Description of reactor design,_ ORNL-TM-0728, 1965.

		## Model citation

		Cite the following references when using this model:

		> F. Bostelmann, S. E. Skutnik, E. Walker, G. Ilas, and W. A. Wieselquist (2021),
		@@ -28,14 +32,14 @@ Cite the following references when using this model:
		> [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.

		: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:

		## Content

		Input and output files for MSRE full core sensitivity and uncertainty
		calculations with the TSUNAMI-Shift sequence are provided.

		: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:

		```
		MSRE
		└── benchmark_fresh_core