Add EBR-II models Refs #487

doc/content/bib/vtb.bib

@@ -2309,4 +2309,80 @@ @techreport{favpro_v1.0_2024
 	title = {{FAVPRO} v1.0 User's Manual},
 	url = {https://www.nrc.gov/docs/ML2411/ML24113A237.pdf},
 	year = {2024}
+
+%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
+% references for the EBR-II SHRT
+
+@article{osti_801571,
+title = {Shutdown and closure of the experimental breeder reactor - II.},
+author = {Michelbacher, J A and Baily, C E and Baird, D K and Henslee, S P and Knight, C J and Rosenberg, K E},
+abstractNote = {The Department of Energy mandated the termination of the Integral Fast Reactor (IFR) Program, effective October 1, 1994. To comply with this decision, Argonne National Laboratory-West (ANL-W) prepared a plan providing detailed requirements to maintain the Experimental Breeder Reactor-II (EBR-II) in a radiologically and industrially safe condition, including removal of all irradiated fuel assemblies from the reactor plant, and removal and stabilization of the primary and secondary sodium, a liquid metal used to transfer heat within the reactor plant. The EBR-II is a pool-type reactor. The primary system contained approximately 325 m{sup 3} (86,000 gallons) of sodium and the secondary system contained 50 m{sub 3} (13,000 gallons). In order to properly dispose of the sodium in compliance with the Resource Conservation and Recovery Act (RCRA), a facility was built to react the sodium to a solid sodium hydroxide monolith for burial as a low level waste in a land disposal facility. Deactivation of a liquid metal fast breeder reactor (LMFBR) presents unique concerns. Residual amounts of sodium remaining in circuits and components must be passivated, inerted, or removed to preclude future concerns with sodium-air reactions that could generate potentially explosive mixtures of hydrogen and leave corrosive compounds. The passivation process being implemented utilizes a moist carbon dioxide gas that generates a passive layer of sodium carbonate/sodium bicarbonate over any quantities of residual sodium. Tests being conducted will determine the maximum depths of sodium that can be reacted using this method, defining the amount that must be dealt with later to achieve RCRA clean closure. Deactivation of the EBR-II complex is on schedule for a March, 2002, completion. Each system associated with EBR-II has an associated layup plan defining the system end state, as well as instructions for achieving the layup condition. A goal of system-by-system layup is to minimize surveillance and maintenance requirements during the interim period between deactivation and decommissioning. The plans also establish document archival of not only all the closure documents, but also the key plant documents (P and IDs, design bases, characterization data, etc.) in a convenient location to assure the appropriate knowledge base is available for decommissioning, which could occur decades in the future.},
+doi = {10.1115/ICONE10-22462},
+url = {https://www.osti.gov/biblio/801571},
+journal = {ICONE-10},
+place = {United States},
+year = {2002},
+month = {9}
+}
+
+@techreport{summer2012benchmark,
+title={Benchmark specifications and data requirements for EBR-II shutdown heat removal tests SHRT-17 and SHRT-45R},
+author={Sumner, Tyler S and Wei, Thomas YC},
+year={2012},
+institution={Argonne National Lab.(ANL), Argonne, IL (United States)}
+}
+
+@article{mochizuki2014benchmark,
+  title={Benchmark analyses for EBR-II shutdown heat removal tests SHRT-17 and SHRT-45R},
+  author={Mochizuki, Hiroyasu and Muranaka, Kohmei and Asai, Takayuki and Van Rooijen, WFG},
+  journal={Nuclear Engineering and Design},
+  volume={275},
+  pages={312--321},
+  year={2014},
+  publisher={Elsevier}
+}
+
+@article{mochizuki2018benchmark,
+  title={Benchmark analyses for EBR-II shutdown heat removal tests SHRT-17 and SHRT-45R--(2) subchannel analysis of instrumented fuel sub-assembly},
+  author={Mochizuki, Hiroyasu and Muranaka, Kohmei},
+  journal={Nuclear Engineering and Design},
+  volume={330},
+  pages={14--27},
+  year={2018},
+  publisher={Elsevier}
+}
+
+@article{mochizuki2010development,
+  title={Development of the plant dynamics analysis code NETFLOW++},
+  author={Mochizuki, Hiroyasu},
+  journal={Nuclear Engineering and Design},
+  volume={240},
+  number={3},
+  pages={577--587},
+  year={2010},
+  publisher={Elsevier}
+}
+
+@techreport{wheeler1976cobra,
+  title={COBRA-IV-I: An interim version of COBRA for thermal-hydraulic analysis of rod bundle nuclear fuel elements and cores},
+  author={Wheeler, CL and Stewart, CW and Cena, RJ and Rowe, DS and Sutey, AM},
+  year={1976},
+  institution={Battelle Pacific Northwest Labs., Richland, Wash.(USA)}
+}
+
+@article{tano2024validation,
+  title={Validation of Pronghorn’s subchannel code using EBR-II shutdown heat removal tests: SHRT-17 and SHRT-45R},
+  author={Tano, Mauricio and Kyriakopoulos, Vasileios and McCay, James and Arment, Tyrell},
+  journal={Nuclear Engineering and Design},
+  volume={416},
+  pages={112783},
+  year={2024},
+  publisher={Elsevier}
+}
+
+@techreport{atz2021ducted,
+  title={Ducted Assembly Steady-State Heat Transfer Software (DASSH): Theory Manual},
+  author={Atz, Milos and Smith, Micheal A and Heidet, Florent},
+  year={2021},
+  institution={Argonne National Lab.(ANL), Argonne, IL (United States)}
 }

doc/content/resources/codes_used.md

@@ -99,9 +99,9 @@ obtained through INL's [NCRC](https://inl.gov/ncrc/).
 - Molten Salt Reactor Experiment RZ multiphysics core model [documentation](msr/msre/multiphysics_rz_model/index.md) and [inputs](https://github.com/idaholab/virtual_test_bed/tree/main/msr/msre/multiphysics_core_model/steady_state)
 
 
-### Pronghorn subchannel
+### SCM
 
-- Subchannel ORNL 19 pins and Toshiba 37 pins benchmarks [documentation](sfr/subchannel/index.md) and [inputs](https://github.com/idaholab/virtual_test_bed/tree/main/sfr/subchannel)
+- SCM validation found in [documentation](sfr/subchannel/index.md) and [inputs](https://github.com/idaholab/virtual_test_bed/tree/main/sfr/subchannel)
 
 
 ## Systems analysis and 1D Thermal-hydraulics

doc/content/resources/input_features.md

@@ -172,7 +172,7 @@ specified. The MRAD and PBMR-400 models listed below are an example of this.
 
 - 1D TRISO fuel depletion [documentation](htgr/triso/triso_model.md) and [inputs](https://github.com/idaholab/virtual_test_bed/tree/main/htgr/triso_fuel)
 
-- Subchannel ORNL 19 pins and Toshiba 37 pins benchmarks [documentation](sfr/subchannel/index.md) and [inputs](https://github.com/idaholab/virtual_test_bed/tree/main/sfr/subchannel)
+- SCM validation found in [documentation](sfr/subchannel/index.md) and [inputs](https://github.com/idaholab/virtual_test_bed/tree/main/sfr/subchannel)
 
 - Dispersed UO2 LEU pulse model [documentation](leu_pulse/index.md) and [inputs](https://github.com/idaholab/virtual_test_bed/tree/main/htgr/leu_pulse)