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Title: Fabrication Characteristics of Large Grain DUPIC Fuel Using SIMFUEL

Abstract

Fabrication characteristics to improve the density and grain size of DUPIC fuel with relation to its fuel performance were experimentally evaluated using SIMFUEL as a surrogate for an actual spent PWR fuel due to the high radioactivity of a spent fuel. Hence, SIMFUELs with a burn-up of 35,000 MWd/tU and 60,000 MWd/tU were used to investigate the influence of fission products contents as an impurity on the fuel powder properties and on the density and grain size of a simulated DUPIC pellet. In order to improve the densification and grain growth of the simulated DUPIC fuel, the effect of the addition of sintering aids was investigated. The specific surface area of the OREOX powders was increased with an increase of the impurities by the dissolved oxides in UO{sub 2} among the impurity groups. The specific surface area of the powders milled after the OXREOX treatment was slightly higher than the UO{sub 2} powder used for a nuclear power plant, thus resulting in sintered pellets with a higher than 95% T.D. (theoretical density). The grain size of the sintered pellets was significantly decreased with increasing amount of the metallic and oxide precipitates. However, on adding the sintering aids such as TiO{submore » 2} and Nb{sub 2}O{sub 5}, the grain size of the sintering aids-doped pellets was greatly improved by up to around 3 times that of the raw pellets and their sintered density was also increased by up to 2%. (authors)« less

Authors:
; ; ; ;  [1]
  1. Korea Atomic Energy Research Institute, 150-1 Duckjin-Dong, 1045 Daedeokdaero, Yuseong, Daejeon Korea, 305-353 (Korea, Republic of)
Publication Date:
Research Org.:
American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
OSTI Identifier:
21229311
Resource Type:
Conference
Resource Relation:
Conference: 2007 LWR Fuel Performance Meeting / TopFuel 2007, San Francisco, CA (United States), 30 Sep - 3 Oct 2007; Other Information: Country of input: France; 8 refs; Related Information: In: Proceedings of the 2007 LWR Fuel Performance Meeting / TopFuel 2007 'Zero by 2010', 683 pages.
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; BURNUP; DENSITY; DOPED MATERIALS; FUEL PELLETS; GRAIN GROWTH; GRAIN SIZE; NIOBIUM OXIDES; NUCLEAR POWER PLANTS; PERFORMANCE; PWR TYPE REACTORS; SIMULATION; SINTERING; SPECIFIC SURFACE AREA; SPENT FUELS; TITANIUM OXIDES; URANIUM DIOXIDE

Citation Formats

Park, Geun IL, Lee, Jung Won, Lee, Jae Won, Yang, Myung Seung, and Song, Kee Chan. Fabrication Characteristics of Large Grain DUPIC Fuel Using SIMFUEL. United States: N. p., 2007. Web.
Park, Geun IL, Lee, Jung Won, Lee, Jae Won, Yang, Myung Seung, & Song, Kee Chan. Fabrication Characteristics of Large Grain DUPIC Fuel Using SIMFUEL. United States.
Park, Geun IL, Lee, Jung Won, Lee, Jae Won, Yang, Myung Seung, and Song, Kee Chan. 2007. "Fabrication Characteristics of Large Grain DUPIC Fuel Using SIMFUEL". United States. doi:.
@article{osti_21229311,
title = {Fabrication Characteristics of Large Grain DUPIC Fuel Using SIMFUEL},
author = {Park, Geun IL and Lee, Jung Won and Lee, Jae Won and Yang, Myung Seung and Song, Kee Chan},
abstractNote = {Fabrication characteristics to improve the density and grain size of DUPIC fuel with relation to its fuel performance were experimentally evaluated using SIMFUEL as a surrogate for an actual spent PWR fuel due to the high radioactivity of a spent fuel. Hence, SIMFUELs with a burn-up of 35,000 MWd/tU and 60,000 MWd/tU were used to investigate the influence of fission products contents as an impurity on the fuel powder properties and on the density and grain size of a simulated DUPIC pellet. In order to improve the densification and grain growth of the simulated DUPIC fuel, the effect of the addition of sintering aids was investigated. The specific surface area of the OREOX powders was increased with an increase of the impurities by the dissolved oxides in UO{sub 2} among the impurity groups. The specific surface area of the powders milled after the OXREOX treatment was slightly higher than the UO{sub 2} powder used for a nuclear power plant, thus resulting in sintered pellets with a higher than 95% T.D. (theoretical density). The grain size of the sintered pellets was significantly decreased with increasing amount of the metallic and oxide precipitates. However, on adding the sintering aids such as TiO{sub 2} and Nb{sub 2}O{sub 5}, the grain size of the sintering aids-doped pellets was greatly improved by up to around 3 times that of the raw pellets and their sintered density was also increased by up to 2%. (authors)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 2007,
month = 7
}

Conference:
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  • The corrosion of SIMFUEL, simulated high-burnup CANDU (CANadian Deuterium Uranium) fuel, was investigated in 0.1 mol{center_dot}dm{sup -3} NaClO{sub 4} solution (pH {approximately} 9.5) as a function of dissolved oxygen concentration using electrochemical techniques and X-ray photoelectron spectroscopy (XPS). Electrodes were constructed of SIMFUEL pellets with compositions close to those of a natural UO{sub 2} fuel that has undergone burnup of 3 at% and 6 at%. The XPS analysis of freshly polished SIMFUEL pellets showed that the extent of uranium oxidation in SIMFUEL was equivalent to that in stoichiometric UO{sub 2}. The SIMFUEL electrodes showed higher conductivity and electrochemical reactivity thanmore » the pure UO{sub 2} electrodes. A comparison of the open circuit corrosion potentials of the SIMFUEL electrodes with that of a pure UO{sub 2} electrode in oxygenated solutions showed a much faster increase in the potential for the SIMFUEL electrodes at short times. This suggests that the initial stages of UO{sub 2} oxidation, i.e., UO{sub 2} {yields} UO{sub 2+x} {yields} UO{sub 2.33}, are facilitated by fission product impurities in the UO{sub 2} matrix. However, the {open_quotes}steady-state{close_quotes} oxidation of uranium in SIMFUEL by the dissolved O{sub 2} was similar to that observed in pure UO{sub 2} under similar conditions.« less
  • A preliminary conceptual design of a Direct Use of spent Pressurized water reactor (PWR) fuel In Canada deuterium uranium (CANDU) reactors (DUPIC) fuel fabrication plant was studied, which annually converts spent PWR fuel of 400 tonnes heavy element (HE) into CANDU fuel. The capital and operating costs were estimated from the viewpoint of conceptual design. Assuming that the annual discount rate is 5% during the construction (5 yr) and operation period (40 yr) and contingency is 25% of the capital cost, the levelized unit cost (LUC) of DUPIC fuel fabrication was estimated to be 616 $/kg HE, which is mostlymore » governed by annual operation and maintenance costs that correspond to 63% of LUC. Among the operation and maintenance cost components being considered, the waste disposal cost has the dominant effect on LUC ({approx}49%). From sensitivity analyses of production capacity, discount rate, and contingency, it was found that the production capacity of the plant is the major parameter that affects the LUC.« less
  • A novel TM020 demountable test cavity has been fabricated by the Spallation Neutron Source (SNS) from large grain niobium ingot sheets. This TM020 cavity is designed to have a demountable test plate at the base of the cavity to allow for measuring RF properties as well as performing surface science analysis in an aim to develop plasma processing as a cleaning method for niobium cavities. Large grain ingot sheet fabrication methods were chosen to reduce the cost of the cavity and to produce smooth surfaces at high electric field locations with standard chemistry techniques, i.e. buffered chemical polish. A novelmore » TM020 demountable test cavity has been fabricated by the Spallation Neutron Source (SNS) from large grain niobium ingot sheets. This TM020 cavity is designed to have a demountable test plate at the base of the cavity to allow for measuring RF properties as well as performing surface science analysis in an aim to develop plasma processing as a cleaning method for niobium cavities. Large grain ingot sheet fabrication methods were chosen to reduce the cost of the cavity and to produce smooth surfaces at high electric field locations with standard chemistry techniques, i.e. buffered chemical polish.« less
  • A comparative study is performed on the three DUPIC fuel bundle design options from the view point of reactor physics. The aspects considered in this study are the power distribution in the bundle and core, the bundle power ripple during refueling the refueling rate and its effect on the electricity cost of DUPIC fuel cycle, and the peak reactor power during 20% Inlet Header Break (IHB) LOCA in CANDU-6 plant. One design option, named DUPIC-A, is chosen as the most desirable among the three proposed ones owing to its superiority in the radial power profile in the bundle, the largestmore » average discharge burnup, and the lowest electricity cost. The peak channel and bundle power for DUPIC-A core are shown to be lowered by 6% and 7%, respectively, than those for the natural uranium core provided the 4-bundle shift fueling scheme is employed.« less
  • During the Dry Process, volatile and semi-volatile elements are released from the fuel. The effects of these released radioactive nuclides on DUPIC fuel cycle are analyzed from the view-point of radiation hazard, decay beat, and hazard index. Radiation hazard of fresh and spent DUPIC fuel is sensitive to the method of Dry Process. Decay beat of the fuel is also affected. Hazard index turned out not to be dependent on Dry Process.