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(U,Gd)O2 FUEL WITH HIGHER CONTENT OF GADOLINIUM OXIDE ...

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PROPERTY INVESTIGATIONS <strong>OF</strong> (U,<strong>Gd</strong>)O 2 <strong>FUEL</strong> <strong>WITH</strong> <strong>HIGHER</strong> <strong>CONTENT</strong> <strong>OF</strong><br />

<strong>GADOLINIUM</strong> <strong>OXIDE</strong><br />

Novikov V.V. (1) , Mikheev E.N. (1) , Lysikov A.V. (1) , Petrov I.V. (2) , Basov V.V. (2) , Lupanin A.S. (2) ,<br />

Pimenov Y.V. (3)<br />

(1) JSC "VNIINM", Russian Federation, 123060, Moscow, Rogova st., 5a<br />

(2) JSC "MSZ" Russian Federation, 144001, Electrostal, Moscow region, Karl Marks st., 12<br />

(3) JSC "TVEL" Russian Federation, 119017, Moscow, B.Ordynka st., 24/26<br />

Abstract<br />

Currently the production of fuel containing above 5 % gadolinium oxide has been started in<br />

Russia. When mastering the fabrication process it has been noted that gadolinium introduced in the<br />

quantity of more then 5 % leads to noticeable changes in fuel properties, viz, density and oxygen to<br />

metal ratio, thermal conductivity and strength characteristics become lower. In the process of<br />

fabrication this type of fuel in subject to more intensive cracking. To resolve the above problems<br />

JSC "MSZ" together with JSC "VNIINM" embarked on improving the fabrication process and<br />

investigating the quality characteristics of fuel pellets containing above 5 % gadolinium oxide.<br />

JSC "VNIINM" and JSC "MSZ" investigated density, oxygen to metal ratio, strength<br />

characteristics, microstructure parameters and thermal stability (resintering) of U-<strong>Gd</strong> pellets with<br />

the aim of their qualification.<br />

At JSC "VNIINM" the procedure has been updated that is used to determine thermal<br />

stability of geometrical sizes and density (resintering) of U-<strong>Gd</strong> fuel pellets for WWER-440 и<br />

WWER-1000 reactors via widening the range of measurement up to the gadolinium oxide content<br />

of 8.5 %.<br />

Introduction<br />

To make up bar the excess initial reactivity, to level off the power in a core and to maintain<br />

the temperature coefficient of reactivity at the specified level, light water reactors of the WWER<br />

type use an integrated burnable poison – gadolinium oxide. The application of gadolinium oxide is<br />

dictated by the properties of gadolinium, i.e., its high neutron absorption section and the burnup rate<br />

that at the optimal composition in close to the rate of uranium-235 burnup. Aside from this, under


2<br />

irradiation of gadolinium no daughter products result that have a high section of thermal neutron<br />

capture while gadolinium oxide and uranium dioxide form solid solutions.<br />

With the current approach to improving the technical and economic NPP parameters via<br />

increasing the nuclear fuel burnup a more efficient suppression of the initial high reactivity is<br />

required. To arrange the suppression the content of a burnable absorber <strong>Gd</strong> 2 O 3 introduced into fuel<br />

has to be more than 5 %. However, from the experience gained in the carried out investigations and<br />

the fabrication of below 5 % <strong>Gd</strong> 2 O 3 containing fuel it is known that the introduction of <strong>Gd</strong> 2 O 3<br />

entails changes in diffusion processes responsible for not only the material densification but also for<br />

the formation of the UO 2 -<strong>Gd</strong> 2 O 3 solid solution [1-3]. The process of the formation of the UO 2 -<br />

<strong>Gd</strong> 2 O 3 solid solution is initiated by the interdiffusion of gadolinium ions into the UO 2 lattice and the<br />

uranium into the <strong>Gd</strong> 2 O 3 lattice. As a result of this interdiffusion the sintering rate decreases and the<br />

densification process is shifted to higher temperatures. The influence of the sintering environment<br />

shows up as different changes in the densities of uranium-gadolinium pellets and uranium dioxide.<br />

Even a little change in the partical pressure of oxygen during sintering may result in an increase of<br />

the UO 2 -<strong>Gd</strong> 2 O 3 solid solution density. The theoretical density of the uranium dioxide-gadolinium<br />

oxide solid solution is lower than that of UO 2 10,96 g/cm 3 and at 10 % of gadolinium oxide<br />

decreases to ~10,63 g/cm3. In this instance the oxygen to metal ratio also changes noticeably. In<br />

practice to calculate the density and the oxygen to metal ratio of U-<strong>Gd</strong> fuel the relationships similar<br />

to (1) and (2) were assumed [4, 5]:<br />

ρu<br />

ρ<br />

g<br />

= ρu<br />

− ⋅ 0, 04 ⋅W<br />

, (1)<br />

ρ<br />

t<br />

K = 2 ,000 + 0, 008W , (2)<br />

where<br />

ρ g is density of U-<strong>Gd</strong> fuel;<br />

ρ u is density of standard UO 2 fuel, from (of) 10,45 to 10,52 g/cm 3 ;<br />

ρ t is theoretical density of UO 2 , 10,96 g/cm 3 ;<br />

K is oxygen to metal ration in U-<strong>Gd</strong> fuel;<br />

W is content of gadolinium oxide, %;<br />

Aside from this, a more than 5 % gadolinium introduction into uranium dioxide leads to<br />

decrease in the thermal conductivity. The increase in the thermal conductivity is related to the fact<br />

that as the content of gadolinium oxide increases the quantity and sizes of pores grow and cracks<br />

appear. The pore formation relates to structural changes in the crystal lattice of fluorite type<br />

uranium dioxide that are effected by introducing gadolinium oxide having the cubic lattice. The


3<br />

thermal conductivity reduction of this type proceeds as the uniformity of the volume distribution of<br />

gadolinium oxide decreases. In its turn, a decrease in the thermal gradients and, thus, to higher<br />

quantities of microcracks. This effect is particularly strong at the <strong>Gd</strong> 2 O 3 content exceeding 5 %<br />

[1,4].<br />

The process used to fabricate U-<strong>Gd</strong> fuel containing below 5 % gadolinium oxide has been<br />

mastered. Besides, in open literature there are sufficient data on the properties of U-<strong>Gd</strong> fuel<br />

containing up to 5 % gadolinium oxide [1-7]. However, the properties of fuel containing more than<br />

5 % gadolinium oxide are studied little [8,9]. For the most part this in explained by the fact that up<br />

to the present time the commercial production of this type of fuel was not a goal. This work is an<br />

attempt to partially make up for the gap.<br />

Investigations<br />

The major properties were investigated at JSC "VNIINM" together with JSC "MSZ" using<br />

laboratory-scale specimens and pellets of pilot batches – produced by JSC "MSZ".<br />

Investigation of density and oxygen to metal ratio<br />

The density of fuel pellets was investigated by the immersion technique. The oxygen to<br />

metal ratio was found by the polarographic method from the transformation of four valence uranium<br />

into six valence one. The results are given in table 1. The same table tabulates of values of density<br />

and oxygen to metal ratio calculated from semiempirical dependences (1) and (2).<br />

Table 1 – Values of density and oxygen to metal ratio<br />

Parameter<br />

Relationship (1) и (2)<br />

Experiment<br />

ρ * g , g/cm 3 К ρ g , g/cm 3 К<br />

<strong>Gd</strong> 2 O 3 , %<br />

1,50 10,46 2,0120 10,52-10,55 2,0126-2,0132<br />

3,35 10,40 2,0268 10,52-10,55 2,0201-2,0227<br />

5 10,33 2,0400 10,50-10,55 2,0302-2,0361<br />

8 10,21 2,0640 10,47-10,54 2,0500-2,0584<br />

10 10,14 2,0800 10,47-10,53 2,0700-2,0767<br />

* For density calculation by relationship (1) ρ u = 10,52 г/см 3 was assumed.<br />

From the data of table 1 it is evident that the semiepirical relationship (1) is not valid. In our<br />

view, this is related to the pellet manufacture process. At the gadolinium oxide content above 5 %


4<br />

oxygen evolved during sintering intensifies diffusion processes, thus increasing the density of the<br />

pellets. At the same time relationship (2) gives adequately exact values of the oxygen to metal ratio<br />

at an increased gadolinium oxide content.<br />

In connection with the revealed difference between theoretically and practically found<br />

densities we have recommended to specify the requirement for the density of uranium-gadolinium<br />

pellets in compliance with the experimentally found data which will allow the provision of the high<br />

uranium loading of a fuel rod and the use of the semiempirical relationship (1) as a reference value<br />

for the lower limit of the density at the specified content of gadolinium oxide.<br />

Investigation in strength characteristics<br />

In compliance with the ASTM requirements C922-00 [9] a pellet loadability test was<br />

performed. For testing three columns of 10 pellets each were used having the gadolinium oxide<br />

contents of 3,35 %, 5,0 %, 8,0 % and 10,0 %. In the experiment it was assumed that all the pellets<br />

had the same density, porosity and grain size. The results are tabulated in table 2 with the<br />

indications of the fracture types: A – a chip of an end face; B – a chip on a face chamfer / an<br />

intersection of a cylindrical surface; C - a chip at pellet cylindrical surface.<br />

It follows from the data of table 2 that at the similar densities, porosity and grain size the<br />

strength of pellets depends of the content of gadolinium oxide and becomes lower with its increase.<br />

Table 2 – Results of investigations for pellet loadability<br />

<strong>Gd</strong> 2 O 3 , % P, kgs Fracture type / quatity<br />

3,35<br />

190 A / 1<br />

305 B / 1<br />

100 B / 1<br />

5<br />

255 C / 1<br />

125 C / 1<br />

60 C / 1<br />

8<br />

225 A /3 , C /1<br />

90 A /1<br />

70 A / 1<br />

10<br />

145 A / 1<br />

70 C / 1<br />

80 B / 1<br />

The influence of grain size on the ultimate strength of U-<strong>Gd</strong> pellets was assessed<br />

qualitatively (figure l) using Griffits modified criterion:<br />

σ = Cd -a , (3)


5<br />

where "C" and "a" are constant determined experimentally; "C" constant accounts for the influence<br />

of other microstructure parameters such as cracks and pore size distribution.<br />

210<br />

200<br />

Ultimate strength, MPa<br />

190<br />

180<br />

170<br />

160<br />

150<br />

5 10 15 20 25 30<br />

Grain size, µm<br />

Figure 1 – U-<strong>Gd</strong> fuel ultimate strength vs grain size<br />

Proceeding from the results of the microstructure examinations this estimation assumed that<br />

"C" constant was similar for the investigated compositions of the U-<strong>Gd</strong> fuel. This assumption<br />

allowed the qualitative assessment of the effect of grain size on the strength of a fuel pellet.<br />

The results of assessing the influence effected by grain size on ultimate strength might be<br />

described by the following dependence:<br />

σ = 266d -0,13(-0,16) . (4)<br />

As it might be seen from figure 1 the "a" exponent is in the range of 0,13-0,16. That is the<br />

acquired results evidence a very weak dependence of the fuel pellet strength on the mean grain size.<br />

This fact corroborates the conclusion that the strength of fuel pellets depends to a greater extent on<br />

the quantity of introduced gadolinium oxide, the method used to prepare initial powder, changes in<br />

the fabrication process conditions, porosity of pellets, phase distribution and grinding.<br />

Investigation of pellet thermal conductivity<br />

The thermal conductivity was investigated using fuel samples containing 5 %, 8 %<br />

gadolinium oxide by laser flash method (Parker impulse method [4]) that consist in measuring the<br />

time interval during which a thermal energy pulse passes through a thin sample (thin discs in our


6<br />

case). The currently acquired and previous data obtained for the 10 % content of gadolinium oxide<br />

were generalized and presented in figure 2. All the data are normalized as applied to the density of<br />

95 % of theoretical via Maxwell-Eiken modified ratio [4].<br />

The presented data comply with theoretical concepts and experimental data on a thermal<br />

conductivity decrease with an increase of the gadolinium oxide content. Thus, they evidence the<br />

needed updating of the process operations used to fabricate fuel containing more than 5 %<br />

gadolinium oxide.<br />

4<br />

3,5<br />

3<br />

♦ - 5 % <strong>Gd</strong> 2 O 3<br />

- 8 % <strong>Gd</strong> 2 O 3<br />

- 10 % <strong>Gd</strong> 2 O 3<br />

λ, W/(mK)<br />

2,5<br />

2<br />

1,5<br />

1<br />

700 800 900 1000 1100<br />

T, K<br />

Figure 2 – Thermal conductivity coefficient of U-<strong>Gd</strong> fuel having different contents of gadolinium oxide<br />

Thermal stability investigations of U-<strong>Gd</strong> fuel<br />

The important parameter of fuel pellets is their thermal stability (resintering). This parameter<br />

affects changes in the pellet geometry (swelling, shrinkage) under irradiation. Previously with the<br />

introduction of up to 5 % gadolinium oxide the test for resintering did not require the introduction<br />

of any special distinctions from the investigations of fuel that did not contain any burnable<br />

absorber. However, at the gadolinium oxide content above 5 % the applied method results in a<br />

significant error. This is explained by the fact that the high temperature thermal treatment of pellets<br />

to determine their resintering usually results in noticeable changes in the oxygen to metal ratio. The<br />

changed oxygen to metal ratio substantially affects the parameter of the (U,<strong>Gd</strong>)O 2 solid solution<br />

crystal lattice. Correspondingly, the reduction leads to an increase in the diameter while the<br />

oxidation results in a decrease in the diameter independent whether pellet resintering takes place or<br />

does not. At low temperatures (not higher than 1400 o C) resintering in as a rule insignificant. In this


7<br />

case dimensions changes are basically effected by a change in the crystal lattice parameter.<br />

Dimensional (diameter) changes might be comparable to changes due to the subsequent high<br />

temperature sintering. To account for the influence effected by the inherent resintering one has to<br />

exclude the influence produced by the changes in a diameter (and density) due to oxidation or<br />

reduction processes, i.e., to determine diametral changes after the high temperature thermal<br />

treatment at the value of the oxygen to metal ratio of the particular pellet that is equal to the<br />

respective initial value. On the basis of the results of the carried out investigations the corrections<br />

factor was suggested that takes into account the changes in the crystal lattice. The introduction of<br />

such a factor provides for the reliable results on the resintering of U-<strong>Gd</strong> fuel.<br />

At JSC "VNIINM" the procedure has been updated that is used to determine the thermal<br />

stability of the geometrical sizes and density (resintering) of fuel pellets of UO 2 containing up to 8,5<br />

% mass fraction of gadolinium oxide as applied to WWER-440 and WWER-1000. The error has<br />

been calculated of determining resintering from a change in the outer diameter ∆D/D for the<br />

resintering range from minus 0,1 % abs. to plus 1,8 % abs. at the confidence level of 0,95.<br />

Investigation of pellets microstructure parameters.<br />

In the fabrication of gadolinium oxide fuel its microstructure parameters were investigated.<br />

The attention was basically placed on its grain sizes, phase composition and the availability and size<br />

of cracks.<br />

The grain sizes, phase composition and available cracks were analyzed metallografically.<br />

All the specimens containing 3,35 %, 5,0 %, 8,0 % and 10,0 % gadolinium oxide were fabricated<br />

using the same process parameters. The results of the investigations are illustrated by figures 3 and<br />

4. The results of examining the phase compositions have revealed that 8,0 % and a higher content of<br />

gadolinium oxide leads to the complete formation of the uranium dioxide – gadolinium oxide solid<br />

solution. At the gadolinium oxide content of 10 % the fraction of the area taken up by the solid<br />

solution is 100 %.<br />

It is evident from the presented data that if the conditions of fabricating fuel having up to 5,0<br />

% gadolinium oxide are used for a higher oxide content then via the oxygen released during<br />

sintering the diffusion processes are intensified with the resultant growth of grain size and the 100<br />

% formation of the solution takes place. However, in this case due to thermal gradients pellets are<br />

subject to intensive cracking (figures 4a and 4 b). Hence, the fuel pellet manufacture conditions<br />

need be corrected. The correction of the fuel process will reduce the formation of cracks in fuel<br />

(figure 4c).


8<br />

Figure 3 – Grain structure of U – 10 % <strong>Gd</strong> 2 O 3 pellets<br />

cracks<br />

homogeneous microstructure (none cracks)<br />

fabrications process updating<br />

Figure 4 – Microstructure of U – 10 % <strong>Gd</strong> 2 O 3 pellets


Commercial optimization of fuel containing above 5 % gadolinium oxide<br />

9<br />

Under the standard conditions the laboratory scale manufactured as well as semicommercially<br />

produced fuel pellets containing above 5,0 % gadolinium oxide have a large quantity<br />

of chips, cracks and microcracks. The pictures of the pellet microstructures before and after<br />

updating the technologic process are illustrated in figure 4.<br />

The analysis has revealed that the appearance of defects is caused by thermal gradients that<br />

are affected by adding gadolinium oxide in the quantity more than 5,0 % and lead to a thermal<br />

resistance increase and a thermal conductivity decrease, hence, to a more intensive formation of<br />

cracks. As it follows from the powder metallurgy practice upon gross alloying with materials that<br />

have properties noticeable different from those of the basic component one has to ensure smooth<br />

thermal loads. Joining into account the results of the start up of the production, the acquired<br />

experimental results as well as the powder metallurgy practice the following proposals were made<br />

on the optimization of the process operations.<br />

JSC "MSZ" together with JSC "VNIINM" have updated the process operations used to<br />

manufacture fuel pellets containing above 5 % gadolinium oxide. In this way the production of the<br />

pellets was ensured that met are the requirement placed by the customer. JSC "MSZ" has produced<br />

a pilot batch of fuel pellets containing 8 % gadolinium oxide. It was delivered to NPP for the trialcommercial<br />

operation.


Conclusions<br />

The implemented comparison of the theoretical dependences of fuel density the oxygen to<br />

metal ration to the experimentally acquired data has shown that:<br />

− in comparison to the semiempiric requirement a more rigid requirement has to be<br />

established for the density that is ensured by the manufacture process this shall allow a<br />

higher uranium load of a fuel rod and the semiempirical dependence to be used as a<br />

reference value for the lower density range at the specified value of the gadolinium oxide<br />

content;<br />

− the oxygen to metal ratio dependence rather will agrees with the experiment, i.e., it might be<br />

used for calculating the detail designs of fuel rods.<br />

From the investigations of the a pellet loadability it follows that at the similar densities,<br />

porosities and grain sizes the strength of pellets depends on the content of gadolinium oxide and<br />

becomes lower with its increase. The implemented qualitative assessment of the influence produced<br />

by a grain size on the strength of U-<strong>Gd</strong> pellets corroborates the conclusion that he fuel pellet<br />

strength to a greater extent depends on the quantity of introduced gadolinium oxide, the method<br />

used to prepare the initial powder, changes in the manufacture process conditions, porosity of<br />

pellets, phase distribution, final treatment (grinding), transport operations during manufacture.<br />

The acquired experimental data are consistent with the theoretical concepts and the<br />

experimentally acquired data on a thermal conductivity reduction with an increase in the content of<br />

gadolinium oxide and necessitate corrections to be introduces into design validations upon the<br />

operation of fuel rod.<br />

The results of the investigations of the fuel phase composition have shown that the content<br />

of gadolinium oxide increased to 8,0 % and higher leads to the complete formation of the uranium<br />

dioxide – gadolinium oxide solid solution.<br />

From the results of the microstructure examinations it follows that at the expense of oxygen<br />

realized during sintering the diffusion processes become intensified with the resultant increases in<br />

grain sizes and pellet densities. However, in this case due to thermal gradients pellets are subject to<br />

gross cracking. Thus, to have high quality products the conditions of the fuel pellet manufacture<br />

have to be perfected.<br />

As applied to the fuels of WWER-440 and WWER-1000 JSC "VNIINM" has updated the<br />

procedure used to determine the thermal stability of geometrical sizes and the density (resintering)<br />

of (U,<strong>Gd</strong>)O 2 pellets having the mass fractions of gadolinium oxide from 3,0 % to 8,5 %. The error<br />

of determining the resintering from changes in the outer diameter ∆D/D in the resintering range


11<br />

from minus 0,1 % abs to plus 0,6 % abs and from a change in the density ∆ρ/ρ in the range from<br />

minus 0,3 % abs to plus 1,8 % abs at the confidence level of 0,95 was calculated.<br />

The existent process used to fabricate the U-<strong>Gd</strong> fuel has been updated which allowed the<br />

output of the products that meet all the requirements placed by the customer.<br />

JSC "MSZ" manufactured a pilot batch of fuel pellets containing 8 % gadolinium oxide and<br />

delivered it to NPP for the trial-commercial operation.


References<br />

1 Bibilashvili Yu.K., Godin Yu.G., Mikheev E.N. et al. Investigation of thermal-physical and<br />

mechanical properties of uranium-gadolinium oxide fuel. Preprint IAE-6138/11. Moscow, 1999, 24<br />

P.<br />

2 Bibilashvili Yu.K., Popov S.G., Proselkov V.N. Thermal properties uranium-gadolinium oxide<br />

fuel pellets. Preprint IAE-6139/11.Moscow,1999 – 44 P.<br />

3 Lysikov A.V., Kouleshov A.V., Novikova E.A. Results of thermal-physical and mechanical<br />

property investigations of modified uranium-gadolinium oxide doped fuel. Russian Scientific<br />

Conference«Materials for Nuclear Technics» – 2007, Zvenigorod – P.22<br />

4 Inoue M., Abe K., Sato I. A method for determining an effective porosity correction factor for<br />

thermal conductivity in fast reactor uranium-plutonium oxide fuel pellets // Journal of Nuclear<br />

Materials – 2000, v.281, №1, P.117-128.<br />

5 Une K. Thermal expansion of UO 2 -<strong>Gd</strong> 2 O 3 fuel pellets// Journal of Nuclear Science and<br />

Technology – 1986, v.23, №11 – P.1020-1022.<br />

6 Bibilashvili Yu.K., Kuleshov A.V., Mikheev E.N. et al. Investigation of thermal-physical and<br />

mechanical properties of uranium-gadolinium oxide fuel // In: Proc. of IAEA Technical Committee<br />

Meeting on Improved Fuel Pellet Materials and Designs – 20-24 October 2003, Brussels, Belgium .<br />

IAEA-TECDOC-1416 – P.85-100.<br />

7 Kolyadin V.I. The thermal conductivity of the uranium dioxide. Preprint IAE-2227, Moscow,<br />

1972, 28 P.<br />

8 Reshetnikov F.G., Bibilashvili Yu.K., Mikheev E.N. et al. Nuclear fuel pellets// RF Patent №<br />

RU 2193242 C2 – 2002.<br />

9 ASTM C922-00 Standard Specification for Sintered Gadolinium Oxide-Uranium Dioxide<br />

Pellets.

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