vault backup: 2025-01-21 11:38:17

.obsidian/plugins/colored-tags/data.json

@@ -172,7 +172,13 @@
     "Geant4-TM": 160,
     "Microreactor-Nuclear": 161,
     "Nu-́cleo": 162,
-    "Root-TM": 163
+    "Root-TM": 163,
+    "microreactor": 164,
+    "Modelica-language": 165,
+    "simplified-model": 166,
+    "System-analysis": 167,
+    "multiphysics": 168,
+    "heat-pipe": 169
   },
   "_version": 3
 }

1 Daily Notes/2025/2025-01-21.md

@@ -33,6 +33,7 @@ where completed
 group by file.name
 ```
 # Calendar Tasks
+-  Microreactor review [startTime:: 11:00]  [endTime:: 11:30]
 -  Edit HACPS hw1 [startTime:: 09:15]  [endTime:: 09:30]
 -  Shower and Breakfast [startTime:: 08:30]  [endTime:: 09:15]
 -  ANS Paper [startTime:: 15:30]  [endTime:: 17:00]

1 Daily Notes/2025/2025-01-22.md

@@ -18,6 +18,7 @@ where !completed
 group by file.name
 ```
 ## What's the plan!
+ - [ ] Figure out how to rectify task lists so they show up in daily tasks #Administrative 
 
 ## What's the results!
 ```dataview

200 Library Papers/gengSimplifiedReactorModel2024.md

@@ -0,0 +1,52 @@
+---
+readstatus: false
+dateread:
+title: "Simplified Reactor Model for Microreactor Coupled with Helium Closed Brayton Cycle"
+year: 2024
+authors:
+
+  
+  - "Geng, Xuyao"
+  
+  - "Wang, Jie"
+  
+
+citekey: "gengSimplifiedReactorModel2024"
+
+journal: "Nuclear Technology"
+
+
+volume: 210
+
+
+issue: 6
+
+
+
+
+
+pages: 941-957
+
+---
+# Indexing Information
+## DOI
+[10.1080/00295450.2023.2273146](https://doi.org/10.1080/00295450.2023.2273146)
+## ISBN
+[](https://www.isbnsearch.org/isbn/)
+## Tags:
+#microreactor, #Modelica-language, #simplified-model, #System-analysis
+
+>[!Abstract]
+>Microreactors comprise a new actively developing class of very small advanced reactors that have the potential to be an alternative to carbon-intensive energy technologies. A microreactor based on high-temperature gas reactor (HTGR) technology is a very promising advanced reactor with inherent safety, and it can couple with a closed Brayton cycle for higher efficiency. Since dynamics characteristics are fundamental to analyzing a power generation system and a reactor is the main source of the dynamics characteristics of a system, it is necessary to study a microreactor model suitable for system analysis. The main goal is to simulate the performance of the previously mentioned integrated system, focusing on the details of the power conversion unit while still ensuring acceptable calculation times. Hence, a simplified reactor model is needed that could supply sufficiently accurate values of pressure drop and heat transfer across the core. In this paper, by simplifying the physical processes in a microreactor, a dynamic model described by differential algebraic equations is obtained based on the lumped parameter modeling methodology and the basic conservation of fluid mass, momentum, and energy. Coupling thermal hydraulics with neutron kinetics, the temperature coefficient of reactivity and xenon poisoning are considered. Finally, the model is programmed and calculated using Modelica language. The transient responses of the main parameters under typical perturbations are analyzed, and the results show that the responses are correct. Because of the effect of reactivity feedback, fluctuations of the main parameters caused by microperturbations eventually tend to stabilize. In addition, the effects of negative reactivity introduced by xenon poisoning under two typical dynamic processes are analyzed. In power regulation, excess reactivity is required to compensate for the negative reactivity introduced by 135Xe. The model and results can properly predict the systematic parameters and serve as a basis for system analysis of microreactor coupling with the helium closed Brayton cycle.
+
+>[!note] Markdown Notes
+>None!
+
+>[!seealso] Related Papers
+>
+
+# Annotations
+
+### Imported: 2025-01-21 11:33 am
+
+

200 Library Papers/matthewsCoupledMultiphysicsSimulations2021.md

@@ -0,0 +1,64 @@
+---
+readstatus: false
+dateread:
+title: "Coupled Multiphysics Simulations of Heat Pipe Microreactors Using DireWolf"
+year: 2021
+authors:
+
+  
+  - "Matthews, Christopher"
+  
+  - "Laboure, Vincent"
+  
+  - "DeHart, Mark"
+  
+  - "Hansel, Joshua"
+  
+  - "Andrs, David"
+  
+  - "Wang, Yaqi"
+  
+  - "Ortensi, Javier"
+  
+  - "Martineau, Richard C."
+  
+
+citekey: "matthewsCoupledMultiphysicsSimulations2021"
+
+journal: "Nuclear Technology"
+
+
+volume: 207
+
+
+issue: 7
+
+
+
+
+
+pages: 1142-1162
+
+---
+# Indexing Information
+## DOI
+[10.1080/00295450.2021.1906474](https://doi.org/10.1080/00295450.2021.1906474)
+## ISBN
+[](https://www.isbnsearch.org/isbn/)
+## Tags:
+#Microreactors, #multiphysics,-MOOSE
+
+>[!Abstract]
+>DireWolf is a multiphysics software driver application designed to simulate heat pipe–cooled nuclear microreactors. Developed under the U.S. Department of Energy, Office of Nuclear Energy Nuclear Energy Advanced Modeling and Simulation (NEAMS) program, the DireWolf software application’s objective is to provide the nuclear community with a design and safety analysis simulation capability. Based upon the NEAMS program Multiphysics Object-Oriented Simulation Environment (MOOSE) computational framework, DireWolf tightly couples nuclear microreactor physics, reactor physics, radiation transport, nuclear fuel performance, heat pipe thermal hydraulics, power generation, and structural mechanics to resolve the interdependent nonlinearities. DireWolf is capable of simulating both steady and transient normal reactor operation and several postulated failure scenarios. We will present the fundamental physics of heat pipe–cooled nuclear microreactors and the MOOSE-based software employed in DireWolf. Both steady and transient results for coupled reactor physics, radiation transport, and nuclear fuel performance are demonstrated.
+
+>[!note] Markdown Notes
+>None!
+
+>[!seealso] Related Papers
+>
+
+# Annotations
+
+### Imported: 2025-01-21 11:33 am
+
+

200 Library Papers/stauffHighFidelityMultiphysicsModeling.md

@@ -0,0 +1,64 @@
+---
+readstatus: false
+dateread:
+title: "High-Fidelity Multiphysics Modeling of a Heat Pipe Microreactor Using BlueCrab"
+year: Error: `format` can only be applied to dates. Tried for format object
+authors:
+
+  
+  - "Stauff, Nicolas E."
+  
+  - "Miao, Yinbin"
+  
+  - "Cao, Yan"
+  
+  - "Mo, Kun"
+  
+  - "Abdelhameed, Ahmed Amin E."
+  
+  - "Ibarra, Lander"
+  
+  - "Matthews, Christopher"
+  
+  - "Shemon, Emily R."
+  
+
+citekey: "stauffHighFidelityMultiphysicsModeling"
+
+journal: "Nuclear Science and Engineering"
+
+
+volume: 0
+
+
+issue: 0
+
+
+
+
+
+pages: 1-17
+
+---
+# Indexing Information
+## DOI
+[10.1080/00295639.2024.2375175](https://doi.org/10.1080/00295639.2024.2375175)
+## ISBN
+[](https://www.isbnsearch.org/isbn/)
+## Tags:
+#heat-pipe, #Microreactor, #multiphysics
+
+>[!Abstract]
+>Researchers who are actively developing nuclear microreactors are planning to employ innovative designs and features using traditional commercial modeling tools that may be inadequate for their design and licensing activities. The codes developed under the U.S. Department of Energy Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) program provide flexibility in terms of geometry modeling and multiphysics coupling and are particularly well suited for modeling novel microreactor concepts. To test the maturity of these codes, this paper introduces a conceptual heat pipe microreactor (HP-MR) designed to gather various technologies of interest to microreactor developers such as control drums, heat pipes, and hydride moderators. The objective of this effort is to demonstrate NEAMS tools capability to perform high-fidelity multiphysics simulations, using coupled neutronics (via the Griffin code), heat conduction (via the BISON code), heat pipe modeling (via the Sockeye code), and hydrogen redistribution in hydride metal moderator (via the SWIFT code). Codes are coupled in-memory through the Multiphysics Object-Oriented Simulation Environment (MOOSE) framework, which permits flexible multiphysics data transfer schemes. The analysis confirmed two key aspects of the HP-MR concept: (1) its ability to follow the power load requested from the heat pipe and (2) its ability to avoid heat pipe cascading failure unless designed with high power close to operating failure limits of its heat pipes. The developed computational model was distributed publicly on the Virtual Test Bed for training purposes to accelerate adoption by industry and to provide a high-fidelity multiphysics solution for benchmarking against other tools. Additional multiphysics analyses including other transients and coupled physics were identified as necessary future work, together with a focus on validating multiphysics behavior against experiments.
+
+>[!note] Markdown Notes
+>None!
+
+>[!seealso] Related Papers
+>
+
+# Annotations
+
+### Imported: 2025-01-21 11:33 am
+
+

3-99 Research/Microreactors.md

@@ -1,11 +1,15 @@
 # What Microreactors are out there?
 Found a really nice review paper
-[[testoniReviewNuclearMicroreactors2021]]
+- [ ] [[testoniReviewNuclearMicroreactors2021]]
 
 # What Models Exist?
 Looks like one group did it. 
-[[aModeladoNucleoAnalisis2023]]
+- [ ] [[aModeladoNucleoAnalisis2023]]
 Published in 2023.
+- [ ] [[gengSimplifiedReactorModel2024]] 
+High Temperature Gas Reactor
 
 Lots of modeling of heat pipes
+- [ ] [[matthewsCoupledMultiphysicsSimulations2021]]
+- [ ] [[stauffHighFidelityMultiphysicsModeling]]