scholarly journals Estimation of the Amounts of Curium and Americium Isotopes in SNF of the BN-600 Reactor

2018 ◽  
Vol 3 (3) ◽  
pp. 460
Author(s):  
E.I. Lukyan ◽  
G.L. Khorasanov ◽  
А.М. Terekhova
Keyword(s):  
Fuel Assembly ◽  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Physical Characteristics ◽  
Reactor Fuel ◽  
Minor Actinides ◽  
Software Complex ◽  
Reactor Fuel Assembly

The neutron-physical characteristics of curium and americium in spent nuclear fuel (SNF) of the BN-600 reactor were considered in the work. With the help of the Serpent software complex, several models of the BN-600 reactor fuel assembly with different enrichment of fuel by U-235 were built. In BN-600, with the probability of dividing Am-241 by no more than 15%, incomplete burning of minor actinides (MA) occurs and even the accumulation of Cm-244, which is dangerous for storage.

scholarly journals Structural seismic characteristics assessment of LMFR fuel assembly hexagonal wrapper over operational temperature range

2019 ◽  
Vol 34 (4) ◽  
pp. 313-324
Author(s):  
M. Khizer ◽  
Zhang Yong ◽  
Yang Guowei ◽  
Wu Qingsheng ◽  
Wu Yican
Keyword(s):  
Fuel Assembly ◽  
Fast Reactor ◽  
Natural Frequencies ◽  
Mass Effect ◽  
Added Mass ◽  
Reactor Fuel ◽  
Temperature Range ◽  
Fast Reactor Fuel ◽  
Lead Bismuth Eutectic ◽  
Reactor Fuel Assembly

In this study, the structural integrity of liquid metal fast reactor fuel assembly has been established for different parameters considering the optimum fuel design. Analytical calculation of added mass effect due to lead bismuth eutectic and verification through previously presented theories, has been established. The integrity of the hexagonal wrapper of fuel assembly has been guaranteed over the entire operating temperature range. Effect of temperature on the density of lead bismuth eutectic, the subsequent change in added mass of lead bismuth eutectic, the effect on natural frequencies and effect on stresses on wrapper, has been studied in detail. A simple empirical relationship is presented for estimation of added mass effect for lead bismuth eutectic type fast reactors for any desired temperature. An approach for assessment of fast reactor fuel assembly performance has been outlined and calculated results are presented. Nuclear seismic rules require that systems and components which are important to safety, shall be capable of bearing earthquake effects and their integrity and functionality should be guaranteed. Mode shapes, natural frequencies, stresses on wrapper and seismic aspect has also been considered using ANSYS. Modal analysis has been compared in vacuum and lead bismuth eutectic using the calculated added mass.

scholarly journals Benchmark exercise for fluid flow simulations in a liquid metal fast reactor fuel assembly

2016 ◽  
Vol 298 ◽  
pp. 218-228 ◽  
Author(s):  
E. Merzari ◽  
P. Fischer ◽  
H. Yuan ◽  
K. Van Tichelen ◽  
S. Keijers ◽  
...  
Keyword(s):  
Fluid Flow ◽  
Liquid Metal ◽  
Fuel Assembly ◽  
Fast Reactor ◽  
Reactor Fuel ◽  
Flow Simulations ◽  
Fast Reactor Fuel ◽  
Reactor Fuel Assembly

Fast spectrum reactor fuel assembly sensitivity analysis

2017 ◽  
Vol 110 ◽  
pp. 1091-1097
Author(s):  
Ryan Stewart ◽  
Chad Pope ◽  
Emerald Ryan
Keyword(s):  
Sensitivity Analysis ◽  
Fuel Assembly ◽  
Reactor Fuel ◽  
Reactor Fuel Assembly

Comparative Stress Analyses of Dropped Spent Nuclear Fuel Assembly in a Prototypal Cask

2021 ◽  
Author(s):  
SAEHANSOL KANG ◽  
Donghyun Kim ◽  
Yoon-suk Chang ◽  
Sanghwan Lee
Keyword(s):  
Fuel Assembly ◽  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Nuclear Fuel Assembly ◽  
Stress Analyses

Heat Transfer Modeling of Spent Nuclear Fuel Using Uncertainty Quantification and Polynomial Chaos Expansion

2017 ◽  
Vol 140 (2) ◽  
Author(s):  
Imane Khalil ◽  
Quinn Pratt ◽  
Harrison Schmachtenberger ◽  
Roger Ghanem
Keyword(s):  
Heat Transfer ◽  
Fuel Assembly ◽  
Uncertainty Quantification ◽  
Nuclear Fuel ◽  
Polynomial Chaos ◽  
Spent Nuclear Fuel ◽  
Polynomial Chaos Expansion ◽  
Complex Case ◽  
Chaos Expansion ◽  
Input Parameters

A novel method that incorporates uncertainty quantification (UQ) into numerical simulations of heat transfer for a 9 × 9 square array of spent nuclear fuel (SNF) assemblies in a boiling water reactor (BWR) is presented in this paper. The results predict the maximum mean temperature at the center of the 9 × 9 BWR fuel assembly to be 462 K using a range of fuel burn-up power. Current related modeling techniques used to predict the heat transfer and the maximum temperature inside SNF assemblies rely on commercial codes and address the uncertainty in the input parameters by running separate simulations for different input parameters. The utility of leveraging polynomial chaos expansion (PCE) to develop a surrogate model that permits the efficient evaluation of the distribution of temperature and heat transfer while accounting for all uncertain input parameters to the model is explored and validated for a complex case of heat transfer that could be substituted with other problems of intricacy. UQ computational methods generated results that are encompassing continuous ranges of variable parameters that also served to conduct sensitivity analysis on heat transfer simulations of SNF assemblies with respect to physically relevant parameters. A two-dimensional (2D) model is used to describe the physical processes within the fuel assembly, and a second-order PCE is used to characterize the dependence of center temperature on ten input parameters.

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