Lead–bismuth eutectic technology for Hyperion reactor

Zhang, J.; Kapernick, Richard J.; McClure, Peter R; Trapp, T.

doi:10.1016/j.jnucmat.2013.04.079

Cited by 28 publications

(6 citation statements)

References 15 publications

Supporting

Mentioning

Contrasting

Unclassified

Order By: Relevance

“…[3] Although there is no operating experience for LBE-cooled reactors outside of Russia, many modular reactor concepts have been studied such as HYPERION, [5] LSPR, [13] PBWFR, [14] SSTAR, [15] and ELSY. Po-210 is a strong alpha emitter with a half-life about 138 days.…”

Section: Assessment Of Lbe As Nuclear Coolantmentioning

confidence: 99%

“…[19,20] The properties are summarized in Table 3. [5] . The thermal expansion coefficient in the table is for the liquid phase, and it cannot be applied to the melting and solidification processes.…”

Section: Lbe Thermal and Physical Propertiesmentioning

confidence: 99%

“…[5] Based on 40-year operating experience with LBE-cooled reactors in Russia, it was concluded that polonium hazards are always overstated and should not preclude the use of LBE as a nuclear coolant. The studies on Po concern were summarized.…”

Section: Polonium Production and Controlmentioning

confidence: 99%

“…[3] Based on the experience, Russian scientists have done extensive research and development of the coolant liquid lead and LBE technology for civilian fast reactors, for example, the small reactor concept SVBR-75/100. [5] In US, the lead-alloy-cooled reactor is one of the Generation IV (Gen. IV) reactor system concepts. Liquid-lead-cooled reactors have been studied in Russia, Japan, Europe, and US.…”

Section: Introductionmentioning

confidence: 99%

See 3 more Smart Citations

Lead–Bismuth Eutectic (LBE): A Coolant Candidate for Gen. IV Advanced Nuclear Reactor Concepts

Zhang

2013

Adv Eng Mater

View full text Add to dashboard Cite

LBE is one of the primary coolant candidates of advanced nuclear reactors. The present review conducts an assessment of the coolant based on a series of liquid metal coolant selection criteria first and then identifies the key concerns of using LBE as the primary coolant of a nuclear reactor. The review focuses on the status of the art of these key concerns: materials degradation, protective oxide layer, and polonium production and control in an LBE coolant system. The review also addresses oxidation kinetics of steels in oxygen-containing LBE, development of oxygen technology and comparisons between LBE and liquid sodium.

show abstract

Section: Assessment Of Lbe As Nuclear Coolantmentioning

confidence: 99%

Section: Lbe Thermal and Physical Propertiesmentioning

confidence: 99%

Section: Polonium Production and Controlmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Lead–Bismuth Eutectic (LBE): A Coolant Candidate for Gen. IV Advanced Nuclear Reactor Concepts

Zhang

2013

Adv Eng Mater

View full text Add to dashboard Cite

show abstract

“…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] …”

unclassified

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

Rowinski¹

View full text Add to dashboard Cite

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.

show abstract

Long-Term Behaviors of Oxide Layer in Liquid Lead–Bismuth Eutectic (LBE), Part II: Model Applications

Zhang

2014

Oxid Met

View full text Add to dashboard Cite

Lead–bismuth eutectic technology for Hyperion reactor

Cited by 28 publications

References 15 publications

Lead–Bismuth Eutectic (LBE): A Coolant Candidate for Gen. IV Advanced Nuclear Reactor Concepts

Lead–Bismuth Eutectic (LBE): A Coolant Candidate for Gen. IV Advanced Nuclear Reactor Concepts

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

Long-Term Behaviors of Oxide Layer in Liquid Lead–Bismuth Eutectic (LBE), Part II: Model Applications

Contact Info

Product

Resources

About