Argonne National Laboratory
Reduced Enrichment for Research and Test Reactors
Nuclear Science and Engineering Division at Argonne
U.S. Department of Energy

Home  :: Foreign Research Reactor Spent Nuclear Fuel :: Related Documents

RERTR Publications



R. B. Pond and J. E. Matos
RERTR Program
Argonne National Laboratory
Argonne, IL 60439

February 1996


PDF version available
DOWNLOAD full paper in PDF format.


Photon dose rates as a function of fission product decay times have been calculated for spent fuel assemblies typical of MTR-type research and test reactors. Based upon these dose rates, the length of time that a spent fuel assembly will be self-protecting (dose rate greater than 100 rem/h at 1 m in air) can be estimated knowing the mass of fuel burned, the fraction of fuel burned, and the fuel assembly specific power density.

The calculated dose rates cover 20 years of fission product decay, spent fuel with up to 80% U-235 burnup and assembly power densities ranging from 0.089 to 2.857 MW/kgU235. Most of the results are unshielded dose rates at 1 m in air with some shielded dose rates at 40 cm in water. Dose rate sensitivity estimates have been evaluated for a variety of MTR fuel assembly designs and for uncertainties in both the physical and analytical models of the fuel assemblies.

The Monte Carlo dose rates reported in this paper are a revision of the dose rates reported in Ref. 1. These dose rates are the result of a revised energy group structure used for the MCNP calculations, and the fluence-to-dose conversion factors for the new group structure. The photon dose rates in air (water) are a factor of 0.85 (0.98) of the old photon dose rates. In addition, this paper presents an analytical method for estimating the photon dose rate of spent fuel, assuming a line-source model of the fission products in a fuel assembly.

Ref. 1: R.B. Pond and J.E. Matos, "Photon Dose Rates from Spent Fuel Assemblies with Relation to Self-Protection", Proc. XVIII International Meeting on Reduced Enrichment for Research and Test Reactors, Paris, France, 17-21 September 1995.


This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

2016 RERTR Meeting

The 2016 International RERTR Meeting (RERTR-2016) will take place in Belgium. Stay tuned for further details.

2015 RERTR Meeting

The 2015 International RERTR Meeting (RERTR-2015) took place in Seoul, Korea on Oct. 11-14, 2015.
For more information visit RERTR-2015.

Useful Links


ARGONNE NATIONAL LABORATORY, Nuclear Engineering Division, RERTR Department
9700 South Cass Ave., Argonne, IL 60439-4814
A U.S. Department of Energy laboratory managed by UChicago Argonne, LLC

Last modified on July 29, 2008 11:33 +0200