The density and thermal expansion of eutectic alloys of lead with bismuth and lithium in condensed state

Stankus, S. V.; Khairulin, R. A.; Mozgovoy, A. G.; Roshchupkin, V. V.; Pokrasin, M. A.

doi:10.1088/1742-6596/98/6/062017

Cited by 15 publications

(11 citation statements)

References 6 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…High swelling of metal fuel is also adjustable by loading fuel with smear density. Nitride fuel seems better than metal fuel in some ways but it produces 14 C by a 14 N (n,p) reaction that needs 15 N enrichment which leads to a significant cost penalty. …”

Section: Fuel Materials Performance: Fuel Typementioning

confidence: 99%

Study for requirement of advanced long life small modular fast reactor

Tak¹,

Choe²,

Jeong³

et al. 2016

AIP Conference Proceedings

View full text Add to dashboard Cite

Section: Fuel Materials Performance: Fuel Typementioning

confidence: 99%

Study for requirement of advanced long life small modular fast reactor

Tak¹,

Choe²,

Jeong³

et al. 2016

AIP Conference Proceedings

View full text Add to dashboard Cite

“…It is not very desirable to use NaK at the irradiation test of a capsule. LBE is a eutectic alloy of lead and bismuth [10] used as a coolant in some nuclear reactors and is a proposed coolant for a lead-cooled fast reactor, as part of the Gen-IV reactor initiative [11]. LBE has significantly higher boiling points as compared to NaK, and thus it can be operated without risk of coolant boiling at higher temperature and it improves thermal efficiency.…”

Section: Capsule With Liquid Metal Thermal Mediamentioning

confidence: 99%

Study on the Effects of Liquid Thermal Media on the Irradiation Capsule of High-Temperature Materials

Cho

Kim

Yang

et al. 2015

Science and Technology of Nuclear Installations

View full text Add to dashboard Cite

Irradiation tests of materials at HANARO have usually been conducted using a standard capsule at temperatures of about 300 ∘ C for irradiation of materials used at PWR. Thus, the standard capsule uses aluminum as the specimen holder, which acts to dissipate the thermal energy. Future nuclear systems such as a VHTR and SFR require the irradiation tests at a relatively high temperature. As an alternative to aluminum which has been used as the thermal media in a standard material capsule, the characteristics of liquid metals such as NaK and LBE are reviewed. The temperatures of the capsule are affected by the variation of parameters such as the gap and wall thickness of the container. In particular, the external gap is most important in determining the temperature of the specimen. LBE raises the temperature of the specimen higher than NaK at the same configuration of the capsule. Thus, LBE can lessen the gap of the parts and reduce the vibration for a stable long-term test in reactor.

show abstract

“…Furthermore, sensitivity studies related to the initial temperature of liquid gallium and the inventory of the water pool, which acts as a heat sink, were also conducted. The properties of liquid gallium compared to other materials are indicated in Tables 1 and 2 [7][8][9][10][11][12]. Figure 1 illustrates the side-cooling concept, where two fluids are separated by a block structure [6].…”

Section: Introductionmentioning

confidence: 99%

Numerical study of in-vessel retention under the gallium–water external reactor vessel cooling system using MARS-LMR

Kang

Park

Kim

et al. 2015

Journal of Nuclear Science and Technology

View full text Add to dashboard Cite

To confirm the feasibility of the gallium-water IVR-ERVCS (in-vessel retention-external reactor vessel cooling system), this paper focuses on the numerical simulation of severe accidents in APR 1400 using MARS-LMR (multidimensional analysis of reactor safety-liquid metal reactor). To analyze the galliumcooled systems, the properties of liquid gallium were added to the MARS-LMR code used in our previous work. In this system, the generated decay heat is transferred to liquid gallium through the reactor pressure vessel and then removed from the water pool as a heat sink. The numerical analyses results show that the temperature range of the liquid gallium is much lower than its boiling point and confirm the natural convection. Sensitivity studies were also performed by changing several parameters such as the initial temperature of gallium and water pool inventory and their results indicated that the working time of the gallium-water IVR-ERVCS depends on the inventory of the water pool. Because liquid gallium in this system does not have a phase change, unlike water, the gallium-water IVR-ERVCS can provide stable and reliable cooling capability. To solve the limitation due to critical heat flux in IVR-ERVCS and to ensure the sufficient thermal margin, it is confirmed that the gallium-water IVR-ERVCS can be a successful severe accident mitigation strategy in nuclear power plants.

show abstract

The density and thermal expansion of eutectic alloys of lead with bismuth and lithium in condensed state

Cited by 15 publications

References 6 publications

Study for requirement of advanced long life small modular fast reactor

Study for requirement of advanced long life small modular fast reactor

Study on the Effects of Liquid Thermal Media on the Irradiation Capsule of High-Temperature Materials

Numerical study of in-vessel retention under the gallium–water external reactor vessel cooling system using MARS-LMR

Contact Info

Product

Resources

About