main.bib

@article{tung_2020,
	title = {{MCS}/{TH1D} analysis of {VERA} whole-core multi-cycle depletion problems},
	volume = {139},
	issn = {18732100},
	doi = {10.1016/j.anucene.2019.107271},
	journal = {Annals of Nuclear Energy},
	author = {Nguyen, Tung Dong Cao and Lee, Hyunsuk and Choi, Sooyoung and Lee, Deokjung},
	month = may,
	year = {2020},
}

@article{kelly_2017,
	title = {{MC21}/{CTF} and {VERA} multiphysics solutions to {VERA} core physics benchmark progression problems 6 and 7},
	volume = {49},
	issn = {2234358X},
	doi = {10.1016/j.net.2017.07.016},
	number = {6},
	journal = {Nuclear Engineering and Technology},
	author = {Kelly, Daniel J. and Kelly, Ann E. and Aviles, Brian N. and Godfrey, Andrew T. and Salko, Robert K. and Collins, Benjamin S.},
	month = sep,
	year = {2017},
	pages = {1326--1338},
}

@article{ma_2019,
	title = {{RMC}/{CTF} multiphysics solutions to {VERA} core physics benchmark problem 9},
	volume = {133},
	issn = {18732100},
	doi = {10.1016/j.anucene.2019.07.033},
	abstract = {High-fidelity life-cycle coupling simulations are attractive for increasing reactor power, increasing the fuel burnup and prolonging the reactor lifetime, which makes reactors much more economical. In this work, the continuous energy Reactor Monte Carlo code RMC was coupled to the subchannel code CTF. With the great support of the high-performance computing techniques, the coupled codes were then used to analyze VERA benchmark Problem 9 for the depletion of the fuel and burnable absorbers in a typical 18-month fuel cycle. Existing Monte Carlo burnup codes suffer from instabilities caused by spatial xenon oscillations. Therefore, a xenon equilibrium correction based on a simplified xenon-iodine burnup chain was used to restrain the spatial xenon oscillations and to improve simulation stability. The neutronics and thermal-hydraulics coupling convergence were investigated in terms of power distribution and Keff. The power distribution and Keff variations show that the neutronics/thermal-hydraulics coupling converges in the third iteration. To verify the neutronics/thermal-hydraulics coupling, the critical boron search algorithm and equilibrium xenon correction method, RMC/CTF solutions to a nominal flow and power critical calculation, VERA Benchmark Problem 7, were compared with the VERA reference solutions (MPACT/CTF) and MC21/CTF. The maximum relative difference of radial assembly power between this work and reference solutions was 2.8\%. For the VERA Benchmark Problem 9, the measured critical boron concentrations were provided to validate coupling codes. The critical boron concentration prediction by RMC/CTF is consistent with the measured boron concentrations with absolute errors within 20 ppm, which is about 200 pcm in reactivity. The RMC/CTF solution for VERA Core Physics Benchmark Problem 9 is the first published coupled Monte Carlo neutronics/subchannel thermal-hydraulics solution for this problem.},
	journal = {Annals of Nuclear Energy},
	author = {Ma, Y. and Liu, Shichang and Luo, Zhen and Huang, Shanfang and Li, Kaiwen and Wang, Kan and Yu, Ganglin and Yu, Hongxing},
	month = nov,
	year = {2019},
	keywords = {Critical boron concentrations, Neutronics and thermal-hydraulics coupling, VERA benchmark, Xenon oscillations},
	pages = {837--852},
}

@inproceedings{nchoi_2020,
	title = {Analytic treatment of intra-fuel-rod temperature distributions in the {GPU}-based continuous energy {Monte} {Carlo} code {PRAGMA}},
	booktitle = {Transactions of the {American} {Nuclear} {Society} {Annual} {Meeting}},
	author = {Choi, Namjae and Joo, Han Gyu},
	year = {2020},
}

@inproceedings{smith_2013,
	address = {Sun Valley, ID},
	title = {Challenges in the {Development} of {High}-{Fidelity} {LWR} {Core} {Neutronics} {Tools}},
	language = {en},
	booktitle = {International {Conference} on {Mathematics} and {Computational} {Methods} {Applied} to {Nuclear} {Science} and {Engineering} ({M}\&{C} 2013)},
	author = {Smith, Kord and Forget, Benoit},
	month = may,
	year = {2013},
}

@phdthesis{ellis,
	type = {Thesis},
	title = {Methods for including multiphysics feedback in {Monte} {Carlo} reactor physics calculations},
	school = {Massachusetts Institute of Technology},
	author = {Ellis, Matthew Shawn},
	year = {2017},
}

@article{chadsey,
	title = {X-ray photoemission calculations},
	volume = {22},
	issn = {0018-9499},
	doi = {10.1109/TNS.1975.4328131},
	number = {6},
	journal = {IEEE Transactions on Nuclear Science},
	author = {Chadsey, W. L. and Wilson, C. W. and Pine, V. W. and Chadsey, W. L. and Wilson, C. W. and Pine, V. W.},
	month = dec,
	year = {1975},
	keywords = {Angular Distribution, Bremsstrahlung, Energy Physics, Monte Carlo Method, Nuclear and High, Photoelectric Emission, Polynomials, Radiation Effects, Spectral Energy Distribution, X Rays},
	pages = {2345-2350},
}

@phdthesis{gries,
	title = {Functional expansion tallies for {Monte} {Carlo} simulations},
	school = {University of Michigan},
	author = {Griesheimer, David},
	year = {2005},
}

@inproceedings{brown,
	title = {Direct sampling of {Monte} {Carlo} flight paths in media with continuously varying cross-sections},
	volume = {2},
	booktitle = {Proc. {ANS} {Mathematics} \& {Computation} {Topical} {Meeting}},
	author = {Brown, Forrest B and Martin, William R},
	year = {2003},
}

@inproceedings{palmtag,
	address = {Jeju, South Korea},
	title = {Modeling {Thermal} {Expansion} in {VERA}-{CS}},
	abstract = {This paper describes the implementation of modeling thermal expansion in the CASL core simulator code VERA-CS. The effects of thermal expansion are first investigated and quantified using single-pin and single-assembly models, and then the effects on full-core calculations are described. This paper shows that the effect of thermal expansion on core-follow critical boron calculations is fairly small (approximately 10 ppm boron), but the effects on ITC and power defect can be significant.},
	booktitle = {Proceeding of {International} {Conference} on {Mathematics} \& {Computational} {Methods} ({M}\&{C} 2017)},
	author = {Palmtag, Scott and Kochunas, Brendan and Jabaay, Dan and Han, Zhuoran and Downar, Thomas},
	year = {2017},
}

@inproceedings{fiorina,
	address = {Portland, OR},
	title = {Detailed modelling of expansion reactivity feedback in fast reactors using {OpenFOAM}},
	language = {en},
	booktitle = {International conference on mathematics and computational methods applied to nuclear science and engineering ({M}\&{C} 2019)},
	author = {Fiorina, C. and Radman, S. and Koc, M.Z. and Pautz, A.},
	year = {2019},
	pages = {1434--1442},
	annote = {American Nuclear Society (ANS).},
}

@article{guo,
	title = {A new neutronics-thermal-mechanics multi-physics coupling method for heat pipe cooled reactor based on {RMC} and {OpenFOAM}},
	volume = {139},
	issn = {0149-1970},
	doi = {https://doi.org/10.1016/j.pnucene.2021.103842},
	abstract = {Based on the characteristics of heat pipe cooled reactors, this study presents a new multi-physics coupling method by employing the Monte Carlo transport code RMC and the open-source code OpenFOAM. Three typical physical processes are considered, i.e., the neutron transport, the heat conduction and the thermal expansion. To conduct the steady-state coupling calculation, an investigation is conducted on the thermal deformation simulation, the expansion reactivity feedback, the mesh mapping and the coupling method between two codes. By employing this method, the coupling calculation on a typical heat pipe cooled reactor named KRUSTY (Kilowatt Reactor Using Stirling TechnologY) is conducted. Compared with the existing results, the correctness of this method is verified. As indicated from the calculation, the reactivity feedback attributed to thermal expansion is dominant, which is nearly 90\% of total reactivity feedback. Specific to fuel deformation, the thermal expansion primarily takes place on the “upper” and “lower” surfaces. As impacted by the high thermal conductivity of fuel, the total temperature difference in the reactor core is sufficiently small, which only reaches about 26K. The results and comparisons reveal the availability and feasibility of this coupling method, and such a method can effectively analyze heat pipe cooled reactors.},
	journal = {Progress in Nuclear Energy},
	author = {Guo, Yuchuan and Li, Zeguang and Huang, Shanfang and Liu, Minyun and Wang, Kan},
	year = {2021},
	keywords = {Heat pipe cooled reactors, KRUSTY, Multi-physics coupling},
	pages = {103842},
}
@article{ma_2021,
	title = {Coupled neutronic, thermal-mechanical and heat pipe analysis of a heat pipe cooled reactor},
	volume = {384},
	issn = {0029-5493},
	doi = {https://doi.org/10.1016/j.nucengdes.2021.111473},
	abstract = {Heat pipe cooled reactors are solid-state, high temperature reactors with significant thermal expansion which influences the neutronics and thermal analyses. The heat pipe operating conditions determine the heat transfer rates and temperature distribution which then affect the core neutronic and thermal–mechanical behavior, especially during heat pipe failure accidents where the radial heat flux is uneven. A two-phase two-dimensional heat pipe model was developed and coupled to a previous neutronic and thermal–mechanical (N/T-M) model. The coupled neutronic, thermal–mechanical and heat pipe heat transfer (N/T-M/HP) strategy is described here with a focus on the iteration schemes, physical mapping and geometry reconstruction. The coupled N/T-M/HP method was then applied to the KRUSTY heat pipe cooled reactor, an experimental solid-state reactor designed to power space missions. The power distribution and reactivity predicted by the coupled method are validated against previous simulations for the KRUSTY design. The heat pipe model predictions are compared with heat pipe experiments which show that the predicted heat pipe wall temperature is within 30 K of the measured temperatures. A steady-state normal operating case and a single heat pipe failure accident were then simulated to show the redundancy and reliability of the solid-state reactor. For the normal case, the thermal–mechanical feedback is ∼850 pcm from the cold state to the hot state. The heat transfer rate into each heat pipe is very stable during the iterations. For the single heat pipe failure accident, the heat pipes adjacent to the failure area are the most affected, with those heat loads increasing from 500 W to 640 W and an operating temperature rising by 16 K. In addition, the single heat pipe failure accident significantly increases the stress concentration in the fuel contacted with the failed heat pipe wall, with the peak stress increasing from 53 MPa to 80 MPa, which is very close to the yield stress. Therefore, the mechanical performance of the solid-state reactor should be carefully analyzed during design and operation.},
	journal = {Nuclear Engineering and Design},
	author = {Ma, Yugao and Han, Wenbin and Xie, Biheng and Yu, Hongxing and Liu, Minyun and He, Xiaoqiang and Huang, Shanfang and Liu, Yu and Chai, Xiaoming},
	year = {2021},
	pages = {111473},
}

@article{imron_2024,
title = {Monte Carlo coupled Multi-Physics with spatially continuous material properties},
journal = {Annals of Nuclear Energy},
volume = {210},
pages = {110856},
year = {2025},
issn = {0306-4549},
doi = {https://doi.org/10.1016/j.anucene.2024.110856},
author = {Muhammad Imron and Deokjung Lee},
}

@article{honarvar,
	title = {Recursive formula to compute {Zernike} radial polynomials},
	volume = {38},
	issn = {0146-9592},
	doi = {10.1364/ol.38.002487},
	number = {14},
	journal = {Optics Letters},
	author = {Honarvar Shakibaei, Barmak and Paramesran, Raveendran},
	month = jul,
	year = {2013},
	pages = {2487},
}

@article{hlee_2020,
	title = {{MCS} – {A} {Monte} {Carlo} particle transport code for large-scale power reactor analysis},
	volume = {139},
	issn = {0306-4549},
	doi = {10.1016/J.ANUCENE.2019.107276},
	journal = {Annals of Nuclear Energy},
	author = {Lee, Hyunsuk and Kim, Wonkyeong and Zhang, Peng and Lemaire, Matthieu and Khassenov, Azamat and Yu, Jiankai and Jo, Yunki and Park, Jinsu and Lee, Deokjung},
	month = may,
	year = {2020},
	pages = {107276},
}

@inproceedings{hlee_2017,
	address = {Jeju, South Korea},
	title = {Preliminary simulation results of {BEAVRS} three-dimensional {Cycle} 1 whole core depletion by {UNIST} {Monte} {Carlo} code {MCS}},
	booktitle = {Proceeding of {International} {Conference} on {Mathematics} \& {Computational} {Methods} ({M}\&{C} 2017)},
	author = {Lee, Hyunsuk and Kim, Wonkyeong and Zhang, Peng and Khassenov, Azamat and Park, Jinsu and Yu, Jiankai and Choi, Sooyoung and Lee, Hwan Soo and Lee, Deokjung},
	year = {2017},
}

@article{yu_2019,
	title = {{MCS} based neutronics/thermal-hydraulics/fuel-performance coupling with {CTF} and {FRAPCON}},
	volume = {238},
	issn = {0010-4655},
	doi = {https://doi.org/10.1016/j.cpc.2019.01.001},
	journal = {Computer Physics Communications},
	author = {Yu, Jiankai and Lee, Hyunsuk and Lemaire, Matthieu and Kim, Hanjoo and Zhang, Peng and Lee, Deokjung},
	year = {2019},
	pages = {1--18},
}

@article{yu_2020,
	title = {Simulations of {BEAVRS} benchmark cycle 2 depletion with {MCS}/{CTF} coupling system},
	volume = {52},
	issn = {1738-5733},
	doi = {https://doi.org/10.1016/j.net.2019.09.007},
	number = {4},
	journal = {Nuclear Engineering and Technology},
	author = {Yu, Jiankai and Lee, Hyunsuk and Kim, Hanjoo and Zhang, Peng and Lee, Deokjung},
	year = {2020},
	pages = {661-673},
}

@inproceedings{woodcock,
	title = {Techniques used in the {GEM} code for {Monte} {Carlo} neutronics calculations in reactors and other systems of complex geometry},
	volume = {557},
	booktitle = {Proc. {Conf}. {Applications} of {Computing} {Methods} to {Reactor} {Problems}},
	publisher = {Argonne National Laboratory},
	author = {Woodcock, E and Murphy, T and Hemmings, P and Longworth, S},
	year = {1965},
	note = {Issue: 2},
}

@article{leppanen_2017,
	title = {On the use of delta-tracking and the collision flux estimator in the {Serpent} 2 {Monte} {Carlo} particle transport code},
	volume = {105},
	doi = {https://doi.org/10.1016/j.anucene.2017.03.006},
	journal = {Annals of Nuclear Energy},
	author = {Leppänen, Jaakko},
	year = {2017},
	pages = {161-167},
}

@inproceedings{ellis_2016,
	title = {Spatially {Continuous} {Depletion} {Algorithm} for {Monte} {Carlo} {Simulations}},
	volume = {1},
	booktitle = {Transactions of the {American} {Nuclear} {Society}},
	publisher = {American Nuclear Society},
	author = {Ellis, Matthew S and Josey, Colin and Forget, Benoit and Smith, Kord},
	year = {2016},
	pages = {1221--1224},
	file = {Attachment:C\:\\Users\\USER\\Zotero\\storage\\SBA8LXFM\\Spatially Continuous Depletion Algorithm for Monte Carlo Simulations.pdf:application/pdf},
}

@article{choi_2021,
	title = {Development of high-fidelity neutron transport code {STREAM}},
	volume = {264},
	doi = {https://doi.org/10.1016/j.cpc.2021.107915},
	journal = {Computer Physics Communications},
	author = {Choi, Sooyoung and Kim, Wonkyeong and Choe, Jiwon and Lee, Woonghee and Kim, Hanjoo and Ebiwonjumi, Bamidele and Jeong, Eun and Kim, Kyeongwon and Yun, Dongmin and Lee, Hyunsuk and Lee, Deokjung},
	year = {2021},
	pages = {107915},
}


@techreport{godfrey,
	title = {{VERA} core physics benchmark progression problem specifications},
	number = {CASL-U-2012- 0131-004},
	institution = {U.S. Department of Energy},
	author = {Godfrey, Andrew T},
	year = {2014},
}

@article{leppanen_2010,
	title = {Performance of {Woodcock} delta-tracking in lattice physics applications using the {Serpent} {Monte} {Carlo} reactor physics burnup calculation code},
	volume = {37},
	issn = {0306-4549},
	doi = {https://doi.org/10.1016/j.anucene.2010.01.011},
	abstract = {This paper presents the delta-tracking based geometry routine used in the Serpent Monte Carlo reactor physics burnup calculation code. The method is considered a fast and efficient alternative to the conventional surface-to-surface ray-tracing, and well suited to the lattice physics applications for which the code is mainly intended. The advantages and limitations of the routine are discussed and the applicability put to test in four example cases. It is concluded that the method performs well in LWR lattice applications, but really shows its efficiency when modeling HTGR particle fuels.},
	number = {5},
	journal = {Annals of Nuclear Energy},
	author = {Leppänen, Jaakko},
	year = {2010},
	pages = {715--722},
}

@inproceedings{hong,
	address = {Jeju, South Korea},
	title = {Advanced {On}-{Line} {Isothermal} {Temperature} {Coefficient} {Measurement} for {A} {Physics} {Test}},
	booktitle = {Transactions of the {Korean} {Nuclear} {Society} {Autumn} {Meeting}},
	author = {Hong, Sun- Kwan},
	year = {2010},
	pages = {135--136},
}

@techreport{ansi,
	title = {Reload {Startup} {Physics} {Tests} for {Pressurized} {Water} {Reactors}},
	language = {en},
	institution = {American Nuclear Society},
	author = {ANSI/ANS-19.6.1-2005},
	year = {2005},
}

@techreport{albagami,
	title = {{TVA} {Watts} {Bar} {Unit} 1 {Multi}-{Physics} {Multi}- {Cycle} {Depletion} {Benchmark} {Version} 2.2},
	number = {NEA/EGMPEBV/DOC(2020)},
	institution = {OECD Nuclear Energy Agency},
	author = {Albagami, T and Rouxelin, P and Abarca, A and Holler, D and Moloko, L and Avramova, M and Ivanov, K and Godfrey, A and Palmtag, S},
	year = {2021},
}

@inproceedings{salko,
	title = {Development of {COBRA}-{TF} for modeling full-core, reactor operating cycles},
	language = {English},
	booktitle = {5th {Topical} {Meeting} on {Advances} in {Nuclear} {Fuel} {Management}, {ANFM} 2015},
	publisher = {American Nuclear Society},
	author = {Salko, Robert K. and Lange, Travis and Kucukboyaci, Vefa and Sung, Yixing and Palmtag, Scott and Gehin, Jess and Avramova, Maria},
	year = {2015},
	keywords = {CASL, COBRA-TF, CRUD, CTF, DNB},
	pages = {178--194},
}

@inproceedings{yu_2017,
	address = {Chengdu, China},
	title = {Preliminary validation of {MCS} multi-physics coupling capability with {CTF}},
	booktitle = {Proceedings of the {Reactor} {Physics} {Asia} 2017 ({RPHA17}) {Conference}},
	author = {Yu, Jiankai and Lee, Hyunsuk and Kim, Hanjoo and Zhang, Peng and Lee, Deokjung},
	year = {2017},
}

@article{ryu_2015,
	title = {Solution of the {BEAVRS} benchmark using the {nTRACER} direct whole core calculation code},
	volume = {52},
	issn = {00223131},
	doi = {10.1080/00223131.2015.1038664},
	number = {7-8},
	journal = {Journal of Nuclear Science and Technology},
	author = {Ryu, Min and Jung, Yeon Sang and Cho, Hyun Ho and Joo, Han Gyu},
	month = aug,
	year = {2015},
	pages = {961--969},
}

@techreport{cole_2021,
	title = {{NRC} {Multiphysics} {Analysis} {Capability} {Deployment} {FY} 2021 - {Part} 2},
	number = {INL/EXT-21-62522},
	institution = {Idaho National Laboratory},
	author = {Cole, M. Mueller and Lin, Ching-Sheng and Ortensi, Javier},
	year = {2021},
}
@article{moose_2020,
	title = {{MOOSE}: {Enabling} massively parallel multiphysics simulation},
	volume = {11},
	issn = {2352-7110},
	doi = {https://doi.org/10.1016/j.softx.2020.100430},
	journal = {SoftwareX},
	author = {Permann, Cody J. and Gaston, Derek R. and Andrš, David and Carlsen, Robert W. and Kong, Fande and Lindsay, Alexander D. and Miller, Jason M. and Peterson, John W. and Slaughter, Andrew E. and Stogner, Roy H. and Martineau, Richard C.},
	year = {2020},
	pages = {100430},
}

@article{leppanen_2013,
author = {Jaakko Leppänen},
title = {Modeling of Nonuniform Density Distributions in the Serpent 2 Monte Carlo Code},
journal = {Nuclear Science and Engineering},
volume = {174},
number = {3},
pages = {318--325},
year = {2013},
publisher = {Taylor \& Francis},
doi = {10.13182/NSE12-54},
}

@article{yu_2018,
	title = {Preliminary coupling of the {Thermal}/{Hydraulic} solvers in the {Monte} {Carlo} code {MCS} for practical {LWR} analysis},
	volume = {118},
	issn = {0306-4549},
	doi = {https://doi.org/10.1016/j.anucene.2018.03.043},
	journal = {Annals of Nuclear Energy},
	author = {Yu, Jiankai and Lee, Hyunsuk and Kim, Hanjoo and Zhang, Peng and Lee, Deokjung},
	year = {2018},
	keywords = {CTF, MCS, Multi-physics Coupling, TH1D},
	pages = {317--335},
}


@article{li_2023,
	title = {A better hash method for high-fidelity {Monte} {Carlo} simulations on nuclear reactors},
	volume = {11},
	issn = {2296-598X},
	doi = {10.3389/fenrg.2023.1161861},
	abstract = {{\textless}p{\textgreater}With the increasing demand for high-fidelity nuclear reactor simulations, the acceleration of Monte Carlo particle transport codes is becoming a core problem. One of the bottlenecks is locating millions or even billions of cells and fetching their associated parameters in the repeated geometry structure. Typically, Monte Carlo codes utilize a hash function to accelerate the cell locating and parameter indexing process. Specifically, they use the “cell vector → hash → parameter” method to accelerate the direct “cell vector → parameter” method. In this work, we propose a better hash method based on the Cyclic Redundancy Check (CRC) mechanism, which has been mathematically proven to be efficient and produce fewer hash collisions. Experimentally, this new hash method has been compared with some other hash functions and showed its superiority in terms of the calculation speed and collision probabilities. This hash method has been integrated into the Reactor Monte Carlo code RMC and worked well in practical applications.{\textless}/p{\textgreater}},
	journal = {Frontiers in Energy Research},
	author = {Li, Kaiwen and An, Nan and Luo, Hao and Huang, Shanfang and Wang, Kan},
	year = {2023},
	file = {Full Text:C\:\\Users\\USER\\Zotero\\storage\\VH2DIBTW\\Li et al. - 2023 - A better hash method for high-fidelity Monte Carlo simulations on nuclear reactors.pdf:application/pdf},
}

@article{imron_otf,
  title={On-the-fly thermal expansion for Monte Carlo multi-physics reactor simulations},
  author={Imron, Muhammad and Lee, Deokjung},
  journal={Frontiers in Nuclear Engineering},
  volume={3},
  pages={1483520},
  year={2024},
  publisher={Frontiers Media SA}
}

@techreport{sieger,
  title={VERA 3.3 release notes},
  author={Sieger, M and Salko Jr, Robert K and Kochunas, Brendan and Adams, Brian and Williamson, Richard},
  year={2015},
  institution={CASL Technical Report: CASL-U-2015-0042-000}
}

@inproceedings{hamilton,
  address = {Knoxville, TN},
  title={Integrated radiation transport and nuclear fuel performance for assembly-level simulations},
  author={Hamilton, Steven and Clarno, Kevin and Philip, Bobby and Berrill, Mark and Sampath, Rahul and Allu, Srikanth},
  booktitle={PHYSOR 2012},
  month = {April},
  year={2012}
}

@article{wang80,
author = {J. Y. Wang and D. E. Silva},
journal = {Appl. Opt.},
keywords = {High power lasers; Optical components; Optical systems; Wavefront aberrations; Wavefronts; Zernike polynomials},
number = {9},
pages = {1510--1518},
publisher = {Optica Publishing Group},
title = {Wave-front interpretation with Zernike polynomials},
volume = {19},
month = {May},
year = {1980},
doi = {10.1364/AO.19.001510},
}