Published August 2019 | Version v1
Miscellaneous Open

Modeling the UO2 ex-AUC pellet process

  • 1. Nuclear Fuel Technology Center, Institute for Technology of Radioactive and Rare Elements, Hanoi (Viet Nam)

Description

Studies on modeling uranium dioxide (UO2) powder and pellet processes from ammonium uranyl carbonate (AUC)- derived uranium dioxide powder (UO2 ex-AUC powder) were reported in the paper. A mathematical model describing the effect of the fabrication parameters on specific surface area (SSA) of UO2 powders was built up. To the best of our knowledge, the Brandon model is used for the first time to describe the relationship between the essential fabrication parameters [reduction temperature (TR), calcination temperature (TC), calcination time (tC) and reduction time (tR)] and SSA of the obtained UO2 powder product. The Brandon model was tested with Wilcoxon's rank sum test, showing a good agreement with the experimental parameters; the model can be used to predict and control the SSA of UO2 powder. Response surface methodology (RSM) based on face centered (CCF), one type of quadratic central composite design (CCD), was used to model the pellet process. The experimental studies on the UO2 pellet process determined region of experimental planning as follows: conversion of AUC into UO2 powder at various temperatures of 773 K, 823 K and 873 K and sintering of UO2 pellets at temperatures of 1923 K, 1973 K and 2023 K for times of 4 h, 6 h and 8 h. On the base of the proposed model, the relationship between the technological parameters and density of the UO2 pellet product was suggested to control the UO2 ex-ADU pellet process as desired levels. The studies on the modeling were implemented at Nuclear Fuel Technology Center (ITRRE). (author)

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Part of:
Vietnam Conference on Nuclear Science and Technology VINANST-13. Agenda and Abstracts

Additional details

Publishing Information

Imprint Title
Vietnam Conference on Nuclear Science and Technology VINANST-13. Agenda and Abstracts
Imprint Pagination
266 p.
Journal Page Range
14 p.
Report number
INIS-VN--004

Conference

Title
13. Vietnam Conference on Nuclear Science and Technology
Original Conference Title
Hoi nghi Khoa hoc va Cong nghe Hat nhan Toan quoc lan thu 13
Acronym
VINANST-13
Dates
7-9 Aug 2019
Place
Ha Long City, Quang Ninh (Viet Nam)

INIS

Country of Publication
Viet Nam
Country of Input or Organization
Viet Nam
INIS RN
51066722
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AMMONIUM COMPOUNDS; CALCINATION; FABRICATION; OXYGEN COMPOUNDS; PELLETS; POWDERS; SPECIFIC SURFACE AREA; URANIUM DIOXIDE
Descriptors DEC
ACTINIDE COMPOUNDS; CHALCOGENIDES; CHEMICAL REACTIONS; DECOMPOSITION; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; PYROLYSIS; THERMOCHEMICAL PROCESSES; URANIUM COMPOUNDS; URANIUM OXIDES

Optional Information

Notes
11 refs, 3 figs, 5 tabs Imprint:Conference program and paper abstracts only; Section E: Radiochemistry and Radiation & Nuclear Chemistry, Nuclear Fuel Cycle, Nuclear Material Science and Technology, Radioactive Waste Management