*Nuclear Thermal Propulsion DOI: http://dx.doi.org/10.5772/intechopen.103895*

on the small nuclear rocket engine design. In: AIAA 2009-5239. 45th AIAA/ASME/SAE/ASEE Joint Propulsion Conference and Exhibit. Denver, Colorado. August 2009

[44] Fittje JE, Borowoski SK, Schnitzler BG. Revised point of departure design options for nuclear thermal propulsion. In: AIAA 2015-4547. AIAA SPACE 2015 Conference and Exposition, Pasadena, CA, USA. August 2015. Available from: https://arc.aiaa.org/doi/10.2514/6.2015- 4547 [Accessed: 10 August 2021]

[45] Nam SH et al. Innovative concept for an ultra-small nuclear thermal rocket utilizing a new moderated reactor. Nuclear Engineering and Technology. 2015;**47**(6):678-699

[46] National Academies of Sciences, Engineering, and Medicine. Space Nuclear Propulsion for Human Mars Exploration. Washington, DC, USA: The National Academies Press; 2021. DOI: 10.17226/25977

[47] Los Alamos National Laboratory. N-Division Personnel. Pewee I Reactor Test Report. Los Alamos National Laboratory Informal Report, LA-4217. Los Alamos, NM, USA: Los Alamos National Laboratory; 1969

[48] Stacy WM. Nuclear Reactor Physics. New York, NY, USA: Wiley; 2007

[49] Gates JT, Denig A, Ahmed R, Mehta VK, Kotlyar D. Low-enriched cermetbased fuel options for a nuclear thermal propulsion engine. Nuclear Engineering and Design. 2018;**331**:313-330. DOI: 10.1016/j.nucengdes.2020.110605

[50] Krecicki M, Kotlyar D. Low enriched nuclear thermal propulsion neutronic, thermal hydraulic, and system design space analysis. Nuclear Engineering and Design. 2020;**363**:110605

[51] Walton JT. An overview of tested and analyzed NTP concepts. NASA

Technical Memorandum 105252, AIAA-91-3503, Conference on Advanced Space Exploration Initiative Technologies, cosponsored by AIAA, NASA, and OAI, Cleveland, Ohio, September 4-6, 1991. Available from: https://ntrs.nasa.gov/api/citations/ 19920001919/downloads/19920001919. pdf [Accessed: 24 March 2022]

[52] Permann CJ et al. MOOSE: Enabling massively parallel multiphysics simulation. SoftwareX. 2020;**11**:100430. Available from: https://www.scienced irect.com/science/article/pii/ S2352711019302973 [Accessed: 24 March 2022]

[53] Kirk BS, Peterson JW, Stogner RH, Carey GH. libMesh: A C++ library for parallel adaptive mesh refinement/ coarsening simulations. Engineering with Computers. 2006;**22**(3–4):237-254. DOI: 10.1007/s00366-006-0049-3

[54] Balay S, et al*.* PETSc Users Manual. ANL-95/11 Rev 3.7. 2016. Available from: https://ntrs.nasa.gov/api/cita tions/20140012915/downloads/ 20140012915.pdf [Accessed: 1 November 2021]

[55] Martineau R et al. Multiphysics for nuclear energy applications using a cohesive computational framework. Nuclear Engineering and Design. 2020; **367**:110751. DOI: 10.1017

[56] Wang Y et al. Rattlesnake: A MOOSE-based multiphysics multischeme radiation transport application. Nuclear Technology;**207**(7): 1047-1072. DOI: 10.1080/ 00295450.2020.1843348

[57] Wang Y et al. Performance improvements for the Griffin transport solvers. In: INL/EXT-21-64272-Rev000. Idaho Falls, ID, USA: Idaho National Laboratory; 2021. Available from: https://inldigitallibrary.inl.gov/sites/sti/ sti/Sort\_50897.pdf [Accessed: 15 September 2021]

[58] Shemon ER et al. PROTEUS-SN User Manual, Revision 1.2. ANL/NE-14/ 6. Chicago, IL, USA: Argonne National Laboratory; 2014

[59] Lee CH et al. MC2-3: Multigroup cross-section generation code for fast reactor analysis. In: ANL/NE-11/41, Rev. 3. Chicago, IL, USA: Argonne National Laboratory; 2018

[60] Schunert S et al. Control rod treatment for FEM based radiation transport methods. Annals of Nuclear Energy. 2019;**127**:293-302

[61] Williamson RL et al. BISON: A flexible code for advanced simulation of the performance of multiple nuclear fuel forms. Nuclear Technology;**207**(7): 954-980. DOI: 10.1080/00295450. 2020.1836940

[62] Hirschhorn J et al. Review and preliminary investigation into fuel loss from cermets composed of uranium nitride and a molybdenum-tungsten alloy for nuclear thermal propulsion using mesoscale simulations. Journal of Materials. 2021;**73**(11):3528-3543. DOI: 10.1007/s11837-021-04873-x. Available from: https://link.springer.com/content/ pdf/10.1007/s11837-021-04873-x.pdf [Accessed: 24 March 2022]

[63] Berry RA et al. RELAP-7 Theory Manual. INL/EXT-14-31366, Rev. 2. Idaho Falls, ID, USA. Available from: https://inldigitallibrary.inl.gov/sites/ sti/sti/6899506.pdf: Idaho National Laboratory; 2016 Accessed: 15 September 2021

[64] Adhikary D, Jayasundara C, Podgorney R, Wilkins A. A robust return-map algorithm for general multisurface plasticity. International Journal for Numerical Methods in Engineering. 2017;**109**(2):218-234. DOI: 10.1002/nme.5284

[65] Wang Y, et al*.* Demonstration of MAMMOTH strongly-coupled

multiphysics simulation with the Godiva benchmark problem. In: M&C 2017 - International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering, Jeju, Korea, April 16-20, 2017. Available from: https://www.kns. org/files/int\_paper/paper/MC2017\_ 2017\_9/P353S09-01WangY.pdf [Accessed: 24 March 2022]

[66] Klein AC, Camp AL, PR MC, Voss SS. Operational Considerations for Fission Reactors Utilized on Nuclear Thermal Propulsion Missions to Mars— A Report to the Nuclear Power & Propulsion Technical Discipline Team. NASA Technical Report NASA/ CR20210000387. Hampton, VA, USA: Langley Research Center; Jan 2021

[67] Xia Y et al. Preliminary Study on the Suitability of a Second-order Reconstructed Discontinuous Galerkin Method for RELAP-7 Thermal-Hydraulic Modeling. INL/EXT-17- 43108-Rev001. Idaho Falls, ID, USA: Idaho National Laboratory; 2017. DOI: 10.2172/1468483

[68] Labouré V et al. Hybrid super homogenization and discontinuity factor method for continuous finite element diffusion. Annals of Nuclear Energy. 2019;**128**:443-454. DOI: 10.1016/j.anucene.2019.01.003

[69] Leppänen J et al. The serpent Monte Carlo code: Status, development, and applications in 2013. Annals of Nuclear Energy. 2015;**82**:142-150. DOI: 10.1016/ j.anucene.2014.08.024

Section 2
