Modeling the UO2 ex-AUC pellet process and predicting the fuel rod temperature distribution under steady-state operating condition

Uranyl ammonium carbonate precipitation and conversion into triuranium octaoxide

“…The precipitants used in these experiments, namely, ammonium carbonate and ammonium hydroxide, were of high commercial purity (minimum of 99%) and were purchased from Shanghai Epoch Material Co., Ltd. Uranyl nitrate solution was derived from nuclear-grade pregnant stripping liquor obtained using Vietnam's yellow cake purification extraction method [ [27] , [28] , [29] , [30] ], which was conducted in-house by the Institute for Technology of Radioactive and Rare Elements (a part of the Vietnam Atomic Energy Institute), using tributyl phosphate as a common solvent used in the extraction of uranium. The use of nuclear-grade uranyl nitrate solution and high-purity precipitants in these experiments ensured the reliability and accuracy of the obtained results, while adhering to the safety regulations and guidelines for the handling of radioactive materials.…”

“…The objective was to identify an AUC precipitate of exceptional purity. Furthermore, previous studies have explored the conversion of AUC (and ADU) powder into ex-AUC (and ex-ADU) UO 2 powder with a range of sintering properties [ [27] , [28] , [29] , [30] ]. Therefore, the primary objective of this study was to provide a thorough and comprehensive study of the AUC process, specifically targeting the production of the ex-AUC U 3 O 8 compound as a potential nuclear fuel material for nuclear research reactors.…”

Predicting behavior of AP-1000 nuclear reactor fuel rod under steady state operating condition by using FRAPCON-4.0 software

“…[5].The main models of FRAPCON-4.0 code used in the calculations include the FRACAS-I thermal-mechanical model and Forsberg-Massih fission gas release model. In the study and our previous [6], the latest version of the steady state fuel performance code, FRAPCON-4.0, was utilized to predict the thermal behavior of fuel rod under steady-state operating condition in reactor. And fuel rod design of AP-1000 designed by Westinghouse Electric Corporation was input data for the code [6][7].…”

“…In the study and our previous [6], the latest version of the steady state fuel performance code, FRAPCON-4.0, was utilized to predict the thermal behavior of fuel rod under steady-state operating condition in reactor. And fuel rod design of AP-1000 designed by Westinghouse Electric Corporation was input data for the code [6][7]. FRAPCON-4.0 software was supported by Vietnam Atomic Energy Agency.…”