scholarly journals Analysis of MOX Fuel Behavior in Halden Reactor by FEMAXI-6 Code

2007 ◽  
Vol 44 (8) ◽  
pp. 1070-1080 ◽  
Author(s):  
Yutaka UDAGAWA ◽  
Motoe SUZUKI ◽  
Toyoshi FUKETA
Keyword(s):  
Mox Fuel ◽  
1997 ◽  
Vol 24 (11) ◽  
pp. 859-870 ◽  
Author(s):  
Yang-Hyun Koo ◽  
Dong-Seong Sohn ◽  
Boris Volkov

Author(s):  
Takayuki Ozawa

A recycle system for minor actinides (MAs) is currently studied to reduce the degree of hazard and the amount of high-level radioactive wastes. In this system, MAs will be recycled by reprocessing and irradiating as mixed oxide (MOX) with plutonium (Pu) and uranium (U) in a fast reactor. It was reported that MA-containing influences up to MA content less than ∼3 wt.% of the heavy metal amount on thermal fuel properties, i.e. melting temperature and thermal conductivity, would be slight. However, MA content of MOX fuels is expected to be ∼5 wt.% in the future recycle system for MAs, and MAs might affect irradiation behavior of MA-MOX fuels. The main influences of MA-containing would be increase of fuel temperature and cladding stress, and the important irradiation behavior of MA-MOX would be fuel restructuring, redistribution, helium (He) generation and cladding corrosion. Several irradiation experiments were performed in experimental fast reactor Joyo to study MA-containing influence on fuel behavior during irradiation. In addition, CEPTAR.V2 was developed so that fuel properties and analysis models would be included to evaluate the MA-MOX fuel behavior during irradiation. In this study, the MA-containing influences were evaluated with CEPTAR.V2 by using the results of highly americium (Am) containing MOX irradiation experiment, B8-HAM, performed in Joyo, and as a consequence, the irradiation behavior of Am-MOX fuels could be precisely analyzed and revealed as the influences of Am content.


2003 ◽  
Vol 40 (12) ◽  
pp. 998-1013 ◽  
Author(s):  
Shin-ichi KOYAMA ◽  
Masahiko OSAKA ◽  
Takashi SEKINE ◽  
Katsufumi MOROZUMI ◽  
Takashi NAMEKAWA ◽  
...  
Keyword(s):  
Mox Fuel ◽  

2003 ◽  
Vol 40 (2) ◽  
pp. 104-113 ◽  
Author(s):  
Isamu SATO ◽  
Toshio NAKAGIRI ◽  
Takashi HIROSAWA ◽  
Sinya MIYAHARA ◽  
Takashi NAMEKAWA

2019 ◽  
Vol 12 (4) ◽  
pp. 50-61
Author(s):  
А. Harutyunyan ◽  
S.B. Vygovskiy ◽  
A. Khachatryan

2020 ◽  
Vol 86 (12) ◽  
pp. 15-22
Author(s):  
N. A. Bulayev ◽  
E. V. Chukhlantseva ◽  
O. V. Starovoytova ◽  
A. A. Tarasenko

The content of uranium and plutonium is the main characteristic of mixed uranium-plutonium oxide fuel, which is strictly controlled and has a very narrow range of the permissible values. We focused on developing a technique for measuring mass fractions of uranium and plutonium by controlled potential coulometry using a coulometric unit UPK-19 in set with a R-40Kh potentiostat-galvanostat. Under conditions of sealed enclosures, a special design of the support stand which minimized the effect of fluctuations in ambient conditions on the signal stability was developed. Optimal conditions for coulometric determination of plutonium and uranium mass fractions were specified. The sulfuric acid solution with a molar concentration of 0.5 mol/dm3 was used as a medium. Lead ions were introduced into the background electrolyte to decrease the minimum voltage of hydrogen reduction to –190 mV. The addition of aluminum nitride reduced the effect of fluoride ions participating as a catalyst in dissolving MOX fuel samples, and the interfering effect of nitrite ions was eliminated by introducing a sulfamic acid solution into the cell. The total content of uranium and plutonium was determined by evaluation of the amount of electricity consumed at the stage of uranium and plutonium co-oxidation. Plutonium content was measured at the potentials, at which uranium remains in the stable state, which makes it possible to subtract the contribution of plutonium oxidation current from the total oxidation current. The error characteristics of the developed measurement technique were evaluated using the standard sample method and the real MOX fuel pellets. The error limits match the requirements set out in the specifications for MOX fuel. The technique for measuring mass fractions of uranium and plutonium in uranium-plutonium oxide nuclear fuel was certified. The relative measurement error of the mass fraction of plutonium and uranium was ±0.0070 and ±0.0095, respectively. The relative error of the ratio of the plutonium mass fraction to the sum of mass fractions of uranium and plutonium was ±0.0085.


2017 ◽  
Author(s):  
David Hurley ◽  
Colby Jensen ◽  
Robert Schley ◽  
Marat Khafizov ◽  
Nirmala Kandadai ◽  
...  

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