Development and application of a safety analysis code for small Lead cooled Fast Reactor SVBR 75/100

Guo, Chao; Lu, Daogang; Zhang, Xun; Sui, Danting

doi:10.1016/j.anucene.2015.03.021

Cited by 21 publications

(9 citation statements)

References 6 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Transient calculations had been performed for typical accidents to ensure the functionality of PRHRS. As a pool‐type reactor with integration and modularization, there are no major pipes of LBE out of the RV of SVBR‐100, which means the loss of coolant accident (LOCA) can be ignored unless the vessel ruptures (Hardly ever) 11,19,20 . Besides, the forced circulation is adopted in SBVR‐100, the performance of natural circulation remains to be verified, and the overheating may occur when the flow decreased.…”

Section: Resultsmentioning

confidence: 99%

“…When ULOF occurs, the pump stopped immediately, the control rods did not move, and the flow rate of the feed water remained constant 20 . Power was adjusted by temperature reactivity coefficients and Doppler reactivity coefficients in this initial stage.…”

Section: Resultsmentioning

confidence: 99%

“…Therefore, the neutron kinetics equations of the point‐reactor were adopted 11,32,34 . Temperature reactivity coefficients and Doppler reactivity coefficients were considered in TACLR, and the coupling of neutronic and thermal‐hydraulic was achieved by iterating the physical and thermal parameters 7,10,18,20 …”

Section: Theories and Schemesmentioning

confidence: 99%

“…The primary loop was divided into several control volumes. Equations for mass, momentum, and energy based on Euler's method were used to describe the thermal‐hydraulic process in each control volume 7,20,35‐37 . The flow rate and pressure response were introduced to simplify the field equations 38‐41 .…”

Section: Theories and Schemesmentioning

confidence: 99%

“…Pengcheng 11 developed the steady‐state thermal analysis codes STAC to analyze a multifunctional small modular natural cycle LFR and used commercial software to verify the correctness. Guo et al 20 simulate ULOF and unprotected transient over power (UTOP) accidents of SVBR‐100 reactor with the self‐developed transient thermal analysis codes, which proved the inherent safety of SVBR‐100. In terms of optimization and evaluation, existing design schemes of PRHRS based on SMLFR usually lack sensitivity and uncertainty propagation rules of parameters. However, the input uncertainties will affect the calculation results, and the influence of different parameters will be various 21‐23 .…”

Section: Introductionmentioning

confidence: 99%

See 4 more Smart Citations

Design and optimization of passive residual heat removal system for lead‐bismuth reactorSVBR‐100

Cheng

Zhang

et al. 2020

Int J Energy Res

View full text Add to dashboard Cite

Summary The passive residual heat removal system (PRHRS) is of great significance to ensure the safety of small modular reactors. In this work, a PRHRS based on the reactor pressure vessel was designed and optimized for the lead‐bismuth reactor SVBR‐100 and an one‐dimensional transient analysis code transient analysis codes for LBE reactor was developed as well. The uncertainty analysis was carried out to identify and optimize the key parameters affecting PRHRS, based on the one‐dimensional physical fields obtained from the primary loop and evaporator. The results of transient calculation showed that the designed PRHRS can effectively remove the heat of the core under the accident of unprotected loss of flow and the station blackout (SBO). The results of sensitivity analysis showed that the maximum temperature of lead‐bismuth eutectic (LBE) was strongly positively correlated with heat capacity and thermal conductivity of the cladding, and was moderately positively correlated with the kinetic coefficient of the pump; The medium negative correlation factor of peak pellet temperature (PPT), peak cladding temperature (PCT), and maximum LBE temperature was the diameter of the sleeve of PRHRS, and therefore, increasing the diameter of the sleeve can improve the performance of the system. The results of uncertainty quantification showed that the output uncertainties of PPT and PCT were larger than those inputs. The uncertainty of LBE temperature was very low, and all thermal parameters in SBO were within safe limits. Finally, the optimized parameters of PRHRS were obtained. This work can provide a reference for the development of designing PRHRS and relevant transient calculation codes for small modular LBE reactors.

show abstract

Section: Resultsmentioning

confidence: 99%

Section: Resultsmentioning

confidence: 99%

Section: Theories and Schemesmentioning

confidence: 99%

Section: Theories and Schemesmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 3 more Smart Citations

Design and optimization of passive residual heat removal system for lead‐bismuth reactorSVBR‐100

Cheng

Zhang

et al. 2020

Int J Energy Res

View full text Add to dashboard Cite

show abstract

Review of fuel assembly design in lead‐based fast reactors and research progress in fuel assembly of China initiative accelerator driven system

Sheng

et al. 2021

Int J Energy Res

View full text Add to dashboard Cite

Summary Lead‐based fast reactor is one of the most promising fourth‐generation nuclear energy systems. Fuel assembly design is a key technology for the research and development of lead‐based fast reactor. The current status of typical lead‐based reactors and fuel assembly design schemes in the world are reviewed in this paper, and also the key technical parameters and design features of fuel assembly are summarized, with the advantages and disadvantages discussed. A hexagonal fuel assembly that can achieve both “passive” and “active” axial positioning by the gravity of ballast unit and mechanical locking device proposed by the nuclear fuel assembly research group of China initiative Accelerator Driven System project at Institute of Modern Physics has been emphatically introduced. It is expected that this paper can provide certain supporting data and reference solutions for the further design and development of fuel assembly for lead‐based reactor.

show abstract

Multi‐objective optimization of thermoeconomic and component size of supercritical carbon dioxide recompression cycle based on small‐scale lead‐cooled fast reactor

Wang

et al. 2022

Intl J of Energy Research

View full text Add to dashboard Cite

Summary When the supercritical CO2 power cycle is employed in confined spaces, such as nuclear‐powered ships and spacecraft, its size should be given priority. To estimate the component size, the one‐dimensional heat exchanger model developed in this study is used in a recompression supercritical CO2 cycle integrated on a small‐scale lead‐cooled fast reactor. A parameter analysis was performed to study the influence of several key parameters on the levelized cost of electricity, thermal efficiency, and system size. Moreover, four types of multi‐objective optimizations were conducted to provide optimization schemes for different scenarios. Results indicated that the increased turbine inlet temperature improved the thermoeconomic but augmented the system volume. The size of the low‐temperature recuperator was observably enlarged near the optimal flow split ratio, thereby increasing the system volume. Pareto optimal solution of bi‐objective optimization based on the levelized cost of electricity and system size reached the lowest system volume of 3.71 m3. Additionally, the best trade‐off result of three‐objective optimization was a thermal efficiency of 42.14%, a levelized cost of electricity of 56.30 $∙MWh−1, and a system volume of 4.43 m3. Meanwhile, maximal and minimal pressure drops of CO2 appeared in the cooler and intermediate heat exchanger, respectively.

show abstract

Development and application of a safety analysis code for small Lead cooled Fast Reactor SVBR 75/100

Cited by 21 publications

References 6 publications

Design and optimization of passive residual heat removal system for lead‐bismuth reactorSVBR‐100

Design and optimization of passive residual heat removal system for lead‐bismuth reactorSVBR‐100

Review of fuel assembly design in lead‐based fast reactors and research progress in fuel assembly of China initiative accelerator driven system

Multi‐objective optimization of thermoeconomic and component size of supercritical carbon dioxide recompression cycle based on small‐scale lead‐cooled fast reactor

Contact Info

Product

Resources

About