Community Research and Development Information Service - CORDIS

Abstract

In the nuclear fuel cycle the reprocessing plant is also used to "account for" the fissile material. The operation takes place in the nuclear accountancy tank, in the input phase, by means of methods which calculate the fissile mass conventionally as a product of the volume and the concentration of the material (U/Pu). There are two types of problem; the first is linked to the reliability and precision of remote measurement of the liquid volume and the second is linked to the plant specific nature of these measurements. The use of tracers with measurement by the IDMS is considered here as the alternative to the traditional techniques. A complete and up-to-date summary of the experiments carried out beginning in 1973 (EUROCHEMIC, Belgium) up to 1986 (ENEA - ITREC, Italy) is examined in detail discussing the tracers used and the results obtained, with a particular emphasis on those cases in which the J.R.C. Ispra participated In this context the methods for separating the tracers (Lu-Mg) from the solutions of spent fuel elements are illustrated as are the methods for mass spectrometry measurements developed and used by the J.R.C. Starting from a critical evaluation of the tracers used, to show the limits of applicability of each one, the results obtained in all the experiments known will be given. The aim is to compare the individual experiments and to suggest some possibilities for use of this technique in the future. Diagrams and tables will show the final uncertainties obtained in the experiments considered and will show their behaviour in time, which passes from the initial uncertainties to an actual value between 0.1 and 1%. The causes and the precautions necessary to reduce them will be considered, to obtain final values of the precision which approach the lower limit (0.5%). A detailed examination will compare the errors associated with the tracer technique with those typical of traditional techniques. The conclusions will summarize and update the survey of the results of the application of the techniques and will direct the interests of the future experiments towards the still existing weak points which have been revealed in this work. Year SITE PLANT Volume (litres) Tracer JRC Participation of the tank 1973 EUROCHEMIC 2,000 Li - 1975 TARAPUR 1,500 Mg - 1976 TARAPUR 1,500 Pb - 1980 W.A.K. 800 U, Li, Mg YES 1982 MARCOULE 500 Mg - 1984 EUROCHEMIC 4,000 Lu, Pb YES 1986 ITREC 200 Lu YES

Additional information

Authors: TRINCHERINI P R JRC ISPRA ESTAB. (ITALY), JRC ISPRA ESTAB. (ITALY)
Bibliographic Reference: INTERNATIONAL SYMPOSIUM ON NUCLEAR MATERIAL SAFEGUARDS, WIEN (AUSTRIA), NOV. 10-14, 1986 WRITE TO CEC LUXEMBOURG, DG XIII/A2, POB 1907 MENTIONING PAPER E 32668 ORA
Availability: Can be ordered online
Record Number: 1989124121600 / Last updated on: 1987-01-01
Category: PUBLICATION
Available languages: en