Post irradiation examination

Post Irradiation Examination (PIE) and fuel behavior is a page devoted to the behaviour of nuclear fuel in a power reactor and the way in which used fuel is studied. It is common that experimental and production fuel will be examined after use in a reactor. [1][2] [3] [4] Due to the intensely radioactive nature of the used fuel this is done in a hot cell. A combination of nondestructive and destructive methods are used.

The PIE is used to check that the fuel is both safe and effective. After major accidents the core (or what is left of it) is normally subject to PIE in order to find out what happened. One site where PIE is done is the ITU which is the EU centre for the study of highly radioactive materials.

Swelling

It is normal for fuel to swell due to thermal expansion during use. A document on the subject can be downloaded from the NASA web site.[5]

Cracking of the fuel

This is due to the fact that as the fuel expands on heating, the core of the pellet expands more than the rim. Because of the thermal stress thus formed the fuel cracks, the cracks tend to go from the centre to the edge in a star shaped pattern.

The temperature of the fuel varies as a function of the distance from the centre to the rim. At distance x from the centre the temperature (T_x) is described by the equation where ρ is the power density (W m^-3) and K_f is the thermal conductivity.

T_x = T_Rim + ρ (r_pellet² - x²) (4 K_f)^-1

To explain this for a series of fuel pellets being used with a rim temperature of 200 ^oC (typical for a BWR) with different diameters and power densities of 250 Wm^-3 have been modeled using the above equation. Note that these fuel pellets are rather large; it is normal to use oxide pellets which are about 10 mm in dimater.

Temperature profile for a 20 mm diameter fuel pellet with a power density of 250 W per cubic meter. Note the central temperature is very different for the different fuel solids.

Temperature profile for a 26 mm diameter fuel pellet with a power density of 250 W per cubic meter.

Temperature profile for a 32 mm diameter fuel pellet with a power density of 250 W per cubic meter.

Temperature profile for a 20 mm diameter fuel pellet with a power density of 500 W per cubic meter. Because the melting point of uranium dioxide is about 3300 K, it is clear that uranium oxide fuel is overheating at the centre

Temperature profile for a 20 mm diameter fuel pellet with a power density of 1000 W per cubic meter. The fuels other than uranium dioxide are not compromised.

Reference Radiochemistry and Nuclear Chemistry, G. Choppin, J-O Liljenzin and J. Rydberg, 3rd Ed, 2002, Butterworth-Heinemann, ISBN 0-7506-7463-6

Fission gas release

As the fuel is degraded or heated the more volatile fission products which are trapped within the uranium dioxide may become free. For example see J.Y. Colle, J.P. Hiernaut, D. Papaioannou, C. Ronchi, A. Sasahara, Journal of Nuclear Materials, 2006, 348, 229.

P. Wood and G.H. Bannister published a paper on the release of ⁸⁵Kr, ¹⁰⁶Ru and ¹³⁷Cs from uranium when air is present. It was found that uranium dioxide was converted to U₃O₈ between about 300 and 500 ^oC in air. They report that this process requires some time to start, after the induction time the sample gains mass. The authors report that a layer of U₃O₇ was present on the uranium dioxide surface during this induction time. They report that 3 to 8% of the krypton-85 was released, and that much less of the ruthenium (0.5%) and cesium (2.6 x 10^-3%) occurred during the oxidation of the uranium dioxide.[6]

The chemical nature of fission products in uranium dioxide fuel and the tempertures required to vapourise each one

A report has been written which contains estimates of the amounts of different isotopes emitted during the chernobyl fire, the fire and explosion at chernobyl is one of the largest releases of radioactivity into the environment which has occured and hence deserves special attention(OECD NEA report on Chernobyl {ten years on}[7])

The chemical forms of fission products in uranium dioxide [8], the percentage release at Chernobyl and the temperatures according to Colle et. al. required to release 10% of an element from either unoxidized or oxidized fuel. When data from one element is assumed to apply to another element the enery is in Italics.

Element	Gas	Metal	Oxide	Solid solution	Radioisotopes	Release at Chernobyl[9]	T required for 10% release from UO2	T required for 10% release from U3O8
Br	Yes	-	-	-	-	-	-	-
Kr	Yes	-	-	-	85Kr	100%	-	-
Rb	Yes	-	Yes	-	-	-	-	-
Sr	-	-	Yes	Yes	89Sr and 90Sr	4-6%	1950 K	-
Y	-	-	-	Yes	-	3.5%	-	-
Zr	-	-	Yes	Yes	95Zr	3.5%	2600 K	-
Nb	-	-	Yes	-	-	-	-	-
Mo	-	Yes	Yes	-	99Mo	>3.5%	-	1200 K
Tc	-	Yes	-	-	-	-	-	1300 K
Ru	-	Yes	-	-	103Ru and 106Ru	>3.5%	-	-
Rh	-	Yes	-	-	-	-	-	-
Pd	-	Yes	-	-	-	-	-	-
Ag	-	Yes	-	-	-	-	-	-
Cd	-	Yes	-	-	-	-	-	-
In	-	Yes	-	-	-	-	-	-
Sn	-	Yes	-	-	-	-	-	-
Sb	-	Yes	-	-	-	-	-	-
Te	Yes	Yes	Yes	Yes	132Te	25-60%	1400 K	1200 K
I	Yes	-	-	-	131I	50-60%	1300 K	1100 K
Xe	Yes	-	-	-	133Xe	100%	1450 K	-
Cs	Yes	-	Yes	-	134Cs and 137Cs	20-40%	1300 K	1200 to 1300 K
Ba	-	-	Yes	Yes	140Ba	4-6%	1850 K	1300 K
La	-	-	-	Yes	-	3.5%	2300 K	-
Ce	-	-	-	Yes	141Ce and 144Ce	3.5%	2300 K	-
Pr	-	-	-	Yes	-	3.5%	2300 K	-
Nd	-	-	-	Yes	-	3.5%	2300 K	-
Pm	-	-	-	Yes	-	3.5%	2300 K	-
Sm	-	-	-	Yes	-	3.5%	2300 K	-
Eu	-	-	-	Yes	-	3.5%	2300 K	-

J.Y. Colle, J.-P. Hiernaut, D. Papaioannou, C. Ronchi and A. Sasahara, Journal of Nuclear Materials, 2006, 348, 229-242 reported the releases of fission products and uranium from uranium dioxide (from spent BWR fuel, burn-up was 65 GWd t^-1) which was heated in a Knudsen cell. Fuel was heated in the Knudsen cell both with and without preoxidation in oxygen at c 650 K. It was found even for the noble gases that a high temperature was required to liberate them from the uranium oxide solid. For unoxidized fuel 2300 K was required to release 10% of the uranium while oxidized fuel only requires 1700 K to release 10% of the uranium.

According to the report on Chernobyl used in the above table 3.5% of the following isotopes in the core were released ²³⁹Np, ²³⁸Pu, ²³⁹Pu , ²⁴⁰Pu, ²⁴¹Pu and ²⁴²Cm.