Community Research and Development Information Service - CORDIS

Abstract

The assessment tools required to demonstrate the safety of a final storage for nuclear waste are computer codes which accommodate the mathematical models describing the physico-chemical processes which occur in the whole system. Identification of release scenarios, modelling of radionuclide transport up to the biosphere and man, dose and risk evaluation are the basic elements of the analysis. The uncertainty which affects the analysis results as a consequence of uncertainties in most of the input data may also be quantified; this is made with the use of statistical codes, which handle data in the form of probability distributions. Four computer code systems are being developed in the European Community, based on these common issues, which enable to consider them as a harmonized set.

Additional information

Authors: BERTOZZI G JRC ISPRA ESTAB. (ITALY) HILL M D NATIONAL RADIOLOGICAL PROTECTION BOARD, CHILTON (UK) LEWI J CEA, FONTENAY-AUX-ROSES FRANCE STORCK R GESELLSCHAFT FUER STRAHLEN- UND UMWELTFORSCHUNG, BRAUNSCHWEIG (GERMANY) , JRC ISPRA ESTAB. (ITALY);NATIONAL RADIOLOGICAL PROTECTION BOARD, CHILTON (UK);CEA, FONTENAY-AUX-ROSES FRANCE;GESELLSCHAFT FUER STRAHLEN- UND UMWELTFORSCHUNG, BRAUNSCHWEIG (GERMANY)
Bibliographic Reference: RADIOACTIVE WASTE MANAGEMENT AND DISPOSAL, LUXEMBOURG (GRAND-DUCHY OF LUXEMBOURG), APRIL 22-26, 1985 WRITE TO CEC LUXEMBOURG, DG XIII/A2, POB 1907 MENTIONING PAPER E 31987 ORA
Availability: Can be ordered online
Record Number: 1989123070500 / Last updated on: 1987-01-01
Category: PUBLICATION
Available languages: en