Prism concept, modular LMR reactors

Salerno, L.N.; Berglund, R.C.; Gyorey, G.L.; Tippets, F.E.; Tschamper, P.M.

doi:10.1016/0029-5493(88)90144-6

Cited by 17 publications

(3 citation statements)

References 1 publication

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“…However, even advanced SFR designs are anticipated to be more expensive than the current light water reactors. This perception contradicts the economic analysis results for some advanced SFR designs, such as European Fast Reactor (EFR) 2 , and US Advanced Liquid Metal Reactor (ALMR) 3 basing on General Electric Company's PRISM 4 design. Both programs predicted that advanced SFRs could achieve similar generating cost as LWRs.…”

Section: Introductionmentioning

confidence: 83%

Improving SFR economics through innovations from thermal design and analysis aspects

Zhao

Zhang

Mousseau

et al. 2009

Nuclear Engineering and Design

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Section: Introductionmentioning

confidence: 83%

Improving SFR economics through innovations from thermal design and analysis aspects

Zhao

Zhang

Mousseau

et al. 2009

Nuclear Engineering and Design

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“…The PRISM design has undergone several iterations since its conception in 1981 and the termination of the ALMR program in 1994. [194][195][196][197][198][199][200][201]…”

Section: Treatment Technologies Developed To Support Ebr-iimentioning

confidence: 99%

Nuclear Fuels and Reprocessing Technologies: A U.S. Perspective

Fredrickson

Yoo

2021

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Reprocessing and/or waste management issues are of concern to the "back end" of the nuclear fuel cycle. Of course, there are a great many "nuclear fuel cycle" scenarios to consider; if not in practice, then at least in theory. The simplest conceptually is the "once through" fuel cycle in which the spent fuel is discarded. The more complex fuel cycle scenarios involve reprocessing spent nuclear fuels and a family of nuclear reactor technologies to accommodate burning and breeding for various military and commercial needs. Therefore, the selection of a specific "fuel cycle" is what ultimately imposes the engineering requirements of the reprocessing and waste management technologies. No one part is independent of the other parts in a fuel cycle flowsheet; all parts should be fully integrated. This paper presents a summary of nuclear chemistry processes, nuclear reactor technologies, associated nuclear fuel types, and the reprocessing technologies that serve the different nuclear fuel types. Comprehending how this series of topics are related to each other is a prerequisite to understanding the requirements of any reprocessing strategy. The summary materials presented here are selective, as opposed to comprehensive. More detailed information on any one subject can be found in the reference materials.

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“…Summary of SMR technology[18][19][20][29][30][31][32][33][34][35][36][37][38][39] [40][41][42][43][44][45][46][47][48][49][50] …”

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Computational fluid dynamics of advanced nuclear reactor cores and its contribution to safety analysis

Rowinski¹

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Analytical methods and Computational Fluid Dynamics (CFD) examined the safety and performance of advanced nuclear reactors. Thermal and pressure drop evaluations of an innovative annular fuel in the European lead-cooled System ELSY fast reactor were conducted. Annular fuel has superior cooling capacity, and for a square fuel lattice, the pressure drop can be lower than the reference value for standard solid fuel. Consequently, when annular fuel rods replace solid fuel rods of the same dimensions the power rating is upgraded. While the hexagonal lattice cools more effectively, the pressure drop is higher than the standard fuel assembly and incompatible with power augmentation. Numerical investigations of supercritical flow of both carbon dioxide and water in a vertical tube under non-uniform heat flux applied at the wall demonstrated that current correlations for the Heat Transfer Coefficient (HTC) at low enthalpy values are accurate to ±15%. At high enthalpy, only the general trend is replicated due to large property value differences near the wall and in the bulk flow. In these circumstances, the thermal conductivity, specific heat, density and viscosity are 5-8 times lower after the transition from sub-to super-critical conditions. Moreover, the efficiency of different HTC correlation models is coolant dependant, e.g. the Swenson* formula proves superior for carbon dioxide, whereas the Ornatsky model** provides better agreement with water, where a lower maximum wall temperature was obtained when a non-uniform heat flux was applied, as compared to the reference case of uniform heat flux. For supercritical water flow inside a 2  2 fuel rod bundle, non-uniform heat flux increases wall temperature beyond the reference uniform flux. Also, wall temperature peaks occur only at the gaps between the fuel rods.

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Prism concept, modular LMR reactors

Cited by 17 publications

References 1 publication

Improving SFR economics through innovations from thermal design and analysis aspects

Improving SFR economics through innovations from thermal design and analysis aspects

Nuclear Fuels and Reprocessing Technologies: A U.S. Perspective

Computational fluid dynamics of advanced nuclear reactor cores and its contribution to safety analysis

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