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|Title:||Reducing the Radioactive Doses of Liquid Samples Taken from Reprocessing Plant Vessels by Volume Reduction|
|Authors:||JANSSENS-MAENHOUT GREET; BUYST JIMMY; PEERANI PAOLO|
|Citation:||NUCLEAR ENGINEERING AND DESIGN vol. 237 p. 880-886|
|Publisher:||ELSEVIER SCIENCE SA|
|JRC Publication N°:||JRC35031|
|Type:||Articles in Journals|
|Abstract:||Size reduction is attractive because it should enable a solution to be analysed by much more direct, and therefore faster and simpler, methods. For instance if the traditional 7 milliliter vials used in reprocessing plants can be replaced by a vessels containing less than one microlitre, it should be possible to analyse the non-diluted solutions in gloveboxes. These vessels would be electro-mechanical, so the term MEMS might be appropriate. This paper determines a conservative estimate for the dose reduction that would be obtained if microlitre samples were extracted from an input accountancy tank at a reprocessing plant, in which the spent fuel is dissolved in nitric acid. This estimate has to take into account the self-shielding e¤ect, that varies for di¤erent low-energy and high-energy gamma-emitting isotopes. The typical composition of the solution from an input accountancy tank in a reprocessing plant is first derived by means of a burnup code. Eight di¤erent spent fuel cases are considered to cover the range of fission products, that can emit low and high energy gamma's. The neutron and gamma fluxes emitted from the classical 7 millilitre vial and from a vessel with less than a microlitre solution are calculated by means of Monte Carlo simulations. The resulting doses are calculated and compared in average and in distribution for di¤erent cases of spent fuel composition. For a volume size reduction of 6300 an averaged conservative dose reduction of 6000 is obtained.|
|JRC Institute:||Institute for the Protection and Security of the Citizen|
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