References
- L.E. Link, et al., Argonne High-Flux Research Reactor-AHFR Conceptual Design Study, Argonne National Laboratory and University of Chicago., 1959.
- R.D. Cheverton, T.M. Sims, "HFIR Core Nuclear Design," ORNL-4621, Oak Ridge National Laboratory, 1971.
- Arne P. Olson, Very-high-flux research reactor concepts, Nucl. Instrum. Methods Phys. Res. A 249 (77-90) (1986). https://doi.org/10.1016/0168-9002(86)90244-5
- P.H. Liem, H. Sekimoto, Neutronic and thermal hydraulic design of the graphite moderated helium-cooled high flux reactor, Nucl. Eng. Des. 139 (221-233) (1993). https://doi.org/10.1016/0029-5493(93)90158-6
- V.K. Raina, et al., Multi-purpose research reactor, Nucl. Eng. Des. 236 (770-783) (2005). https://doi.org/10.1016/j.nucengdes.2005.09.022
- C.G. Seo, et al., Conceptual Core Design of a 20 MWResearch Reactor Using the HANARO Fuel Assembly, Transactions of the Korean Nuclear Society Spring Meeting Chuncheon, Korea, 2006.
- R.T. Primm III, et al., Design Study for a Low-Enriched Uranium Core for the High Flux Isotope Reactor, Annual Report for FY, 2007, p. 2007.
- F.E. Teruel, Rizwan-uddin, An innovative research reactor design, Nucl. Eng. Des. 239 (395-407) (2009). https://doi.org/10.1016/j.nucengdes.2008.10.025
- S.B. Chafle, et al., High Flux Research Reactor, Peaceful Uses of Atomic Energy, 2009.
- C.G. Seo, N.Z. Cho, A core design concept for multi-purpose, Nucl. Eng. Des. 252 (34-41) (2012). https://doi.org/10.1016/j.nucengdes.2012.06.031
- L.P. Foyto, et al., The University of Missouri Research Reactor HEU to LEU Fuel Conversion Project Status, 2013.
- A. Bergeron, et al., "Low Enriched Uranium Core Design for the Massachusetts Institute of Technology Reactor (MITR) with Un-finned 12 Mil-Thick Clad UMo Monolithic Fuel", ANL/GTRI/TM-13/15, Argonne National Laboratory, 2013.
- E.E. Feldman, et al., "Technical Basis in Support of the Conversion of the University of Missouri Research Reactor (MURR) Core from Highly-Enriched to Low Enriched Uranium-Steady-State Thermal Hydraulic Analysis" ANL/RERTR/TM-12-37 REV, vol. 1, 2013.
- R. Vignolo, et al., "Conceptual Design of a Compact Nuclear Reactor Core" Conference Paper, IGORR Conference, 2014.
- D.J. Diamond, et al., "Conversion Preliminary Safety Analysis Report for the NIST Research Reactor", BNL-107265-2015-IR, Brookhaven National Laboratory, 2014.
- Z. Wu, "A Research Reactor Core Design for Advanced Neutron Source" Proceeding of the 2017 25th International Conference on Nuclear Engineering ICONE25, 2017. Shanghai, China-ICONE 25-67573.
- B.R. Betzler, et al., High-Fidelity Modeling and Simulation for a High Flux Isotope Reactor Low-Enriched Uranium Core Design, 2017.
- M.D. Dehart, et al., Fuel Element Design and Analysis for Potential LEU Conversion of the Advanced Test Reactor, 2017.
- J.R. Askew, F.J. Fayers, P.B. Kemshell, General description of the lattice code WIMS, Atomic Energy Establ. Winfrith, Eng. (1966).
- T.B. Flower, et al., "Nuclear Reactor Core Analysis Code: CITATION" ORNL-TM-2496, Oak Ridge National Laboratory, 1971.
- D. Basile, et al., "COBRA-EN: an Upgraded Version of the COBRA-C/MIT Code for Thermal-Hydraulic Transient Analysis of Light Water Reactor Fuel Assemblies and Cores" Report 1010/1, ENEL CRTN, Milano, 1999.
- Groenveld, et al., The 2006 CHF look-up table, Nucl. Eng. Des. 237 (2007) 1909-1922. https://doi.org/10.1016/j.nucengdes.2007.02.014
- "Final Safety Analysis Report, Chapter 4 (Reactor) for Bushehr Nuclear Power Plant" by Joint-Stock Association, ATOMSTPOYEXPORT, Moscow, 2007.
- D.B. Pelowitz, MCNPXTM User's Manual Version 2.6.0, LOS ALAMOS NATIONAL LABORATORY, 2008.
- M.H. Porhemmat, K. Hadad, F. Faghihi, PARCS cross-section library generator; part one: development and verification, Prog. Nucl. Energy 78 (2015) 155-162. https://doi.org/10.1016/j.pnucene.2014.08.008
- M.H. Porhemmat, K. Hadad, M. Mahzoon, Modular ray tracing in 2D whole core transport with MOC, Prog. Nucl. Energy 99 (2017) 103-109. https://doi.org/10.1016/j.pnucene.2017.05.005
- M.H. Porhemmat, K. Hadad, S. Dulla, P. Ravetto, Verification and validation of the modular ray tracing MOC using the coupled forward-adjoint approach and application to C5G7 benchmark, Ann. Nucl. Energy 129 (2019) 13-20. https://doi.org/10.1016/j.anucene.2019.01.041
- H.J. Kretzschmar, W. Wagner, International Steam Tables Properties of Water and Steam Based on the Industrial Formulation IAPWS-IF97, third ed., 2018.
- Guidelines for Preparing and Reviewing Applications for the Licensing of Nonpower Reactors, Standard Review Plan and Acceptance Criteria, 1996. U.S. NRC, NUREG-1537, part 2.
Cited by
- Comparison of semi-heavy water and H2O as coolant for a conceptual research reactor from the view point of neutronic parameters vol.118, 2020, https://doi.org/10.1016/j.pnucene.2019.103126
- The development of fuel management code TRACS for HFETR based on Unstructured-mesh variational nodal method vol.166, 2022, https://doi.org/10.1016/j.anucene.2021.108807