All uranium nuclides are radioactive. Thus, also natural uranium is radioactive; it mainly consists of the nuclides U-238 and U-235 and also contains U-234 in radioactive equilibrium with U-238.
Because of the very long half-lives of U-238 ($t_{1/2}=4.468\times10^9\ \mathrm a$) and U-235 ($t_{1/2}=7.04\times10^8\ \mathrm a$), however, the specific activity of natural uranium is relatively low.
The total specific activity in freshly purified natural uranium is about $2.5\times10^7\ \mathrm{Bq/kg}$ (i.e. not just $15\ \mathrm{Bq/kg}$. The nuclide-specific activity in $1\ \mathrm{kg}$ freshly purified natural uranium is given in the following table.
$$\textbf{Activity in 1 kg natural uranium}\\
\begin{array}{ll}
\hline
\text{Nuclide} & \text{Activity}\ a\ \text{in Bq}\\
\hline
\text{U-238} & 1.2\times10^7\\
\text{U-235} & 5.8\times10^5\\
\text{U-234} & 1.2\times10^7\\
\hline
\end{array}$$
During the chemical purification of the uranium sample, the various daughter nuclides are removed. Due to radioactive decay of uranium, however, new daughter nuclides of the uranium nuclides are generated. For example, after a waiting time of one year, the total specific activity of natural uranium and its daughter products has approximately doubled to $5.0\times10^7\ \mathrm{Bq/kg}$. The nuclide-specific activity in $1\ \mathrm{kg}$ natural uranium after one year is given in the following table (only nuclides with activity above $1\ \mathrm{Bq}$ are shown).
$$\textbf{Activity in 1 kg natural uranium including daughter nuclides after 1 a}\\
\begin{array}{ll}
\hline
\text{Nuclide} & \text{Activity}\ a\ \text{in Bq}\\
\hline
\text{U-238} & 1.2\times10^7\\
\text{U-235} & 5.8\times10^5\\
\text{U-234} & 1.2\times10^7\\
\text{Pa-231} & 1.2\times10^1\\
\text{Pa-234} & 2.0\times10^4\\
\text{Pa-234m} & 1.2\times10^7\\
\text{Th-230} & 1.1\times10^2\\
\text{Th-231} & 5.8\times10^5\\
\text{Th-234} & 1.2\times10^7\\
\hline
\end{array}$$
The dose rate due to external exposure caused by a $1\ \mathrm{kg}$ natural uranium sample depends on the geometry. Assuming a simple point source geometry in a typical working distance of $0.5\ \mathrm m$, the effective dose rate only from uranium nuclides may be estimated as $8.0\times10^{-5}\ \mathrm{mSv/h}$. If also the daughter nuclides generated after one year are taken into account, the total effective dose rate increases to $2.9\times10^{-4}\ \mathrm{mSv/h}=0.29\ \mathrm{\mu Sv/h}$, which could be easily measured in addition to the average ambient background dose rate of about $0.1\ \mathrm{\mu Sv/h}$. Therefore, most of the external exposure caused by natural uranium is due to daughter nuclides and not due to the uranium nuclides themselves.
A $1\ \mathrm{kg}$ natural uranium sample, however, is not a point source. For example, assuming a spherical geometry, the sphere would have a diameter of about $4.7\ \mathrm{cm}$. Because of the high density of uranium, most of the radiation emitted by the uranium sample is absorbed by the material itself. In a typical working distance of $0.5\ \mathrm m$ to such a sphere, the effective dose rate from uranium nuclides may be estimated as $8.5\times10^{-7}\ \mathrm{mSv/h}$. If also the daughter nuclides generated after one year are taken into account, the total effective dose rate is $2.8\times10^{-5}\ \mathrm{mSv/h}$. Therefore, the dose rate for a real sample is significantly lower than the dose rate for a point source. This effect is called self-absorption. (This effect is especially noticeable when you measure the dose rate at new fuel assemblies of a pressurized water reactor, which consist of uranium dioxide in fuel rods with a typical active length of about $4\ \mathrm m$ but a diameter of less than $1\ \mathrm{cm}$. Due to self-absorption, the dose rate is much lower when looking from the top or bottom compared to the sides.)
Assuming a working time of $2\,000\ \mathrm h$ per year, working with such samples would result in an effective dose of $0.056\ \mathrm{mSv}$ per year. This dose is well below the usual dose limit for radiation workers of $20\ \mathrm{mSv}$ per year.
Compared to the dose from external exposure, the dose from internal exposure caused by the intake of radioactive material can be more important since the distances of the relevant tissues to the source are obviously much shorter and self-absorption by the radioactive material is not relevant. Especially alpha radiation can be very important for internal exposure although it is not relevant for external exposure at all.
Obviously, intake of a $1\ \mathrm{kg}$ uranium sphere is not realistic. However, ingestion of $1\ \mathrm g$ of uranium in the form of uranium dioxide dust might be considered, for example if unprotected workers often contaminate their hands and later touch their food. The resulting committed effective dose (delivered over 50 years) after ingestion of $1\ \mathrm g$ of natural uranium including daughter nuclides generated after one year (with a total activity of $5.0\times10^4\ \mathrm{Bq}$) may be estimated as $0.090\ \mathrm{mSv}$ (using new dose coefficients taken from ICRP Publication 137). Therefore, when working with uranium, contamination can be a more important problem than external exposure.
The committed effective dose from ingestion of uranium dioxide is still relatively low. The main reason is the low uptake of relatively insoluble uranium compounds from the gastrointestinal tract to the blood. Only a fraction of about $0.2\ \%$ of the uranium nuclides are assumed to be absorbed after ingestion.
Different results are obtained for inhalation, when such insoluble uranium compounds are deposited in the lungs. Assuming inhalation of $100\ \mathrm{mg}$ of natural uranium in the form of uranium dioxide particulate aerosols with an effective diameter of $1\ \mathrm{\mu m}$ including daughter nuclides generated after one year (with a total activity of $5.0\times10^3\ \mathrm{Bq}$), the resulting committed effective dose (delivered over 50 years) may be estimated as $20\ \mathrm{mSv}$. This value corresponds to the annual dose limit for radiation workers. Therefore, the most important problem when working with uranium (or similar relatively insoluble alpha emitters) is inhalation of airborne contamination.