Cel The objective of the AHE experiment is to investigate radiological aspects of handling high-level waste (either spent fuel or vitrified high level waste) in an underground repository. Neutron dose rates are measured resulting from direct radiation and from neutrons scattered by the surrounding host rock (rock salt). Computer codes and model calculations are to be verified by these experiments. Thus, an experimentally validated tool will be available for future detailed repository planning with emphasis on minimizing the radiation exposure of the operating personnel.The project was a demostration test which was reformed by DBE and ANDRA/CEA in the Asse mine. The objective of this experiment was to investigate radiological aspects of handling spent fuel/high level waste in the drifts of an underground repository in a salt dome. As neutrons play an important role in the direct disposal option, main emphasis was laid on their contribution to total dose rate. Due to the narrow drift dimensions, backscattering of the neutrons from the drift walls had to be expected, thus increasing the dose rate for the operating personnel.The experimental results showed that the intensity od neutron backscattering from the drift walls depends upon the drift cross section and the position of the cask within the drift. The equivalent dose rate in the near-field of the cask during underground handling was two to three times higher that above ground. Predictions performed with the Monte Carlo programmes MORSE, MCNP and TRIPOLI were in excellent agreement with the experimental findings. Thus, validated computer codes are available for future detailed repository planning with emphasis on minimising radiation exposure of the operating personnel.Work programme:Design planning 1991/1992Implementation planning 1992Construction and acquisition 1992/1993Execution and disposal 1993/1994Evaluation and description 1994 From a more practical point of view, the programme can be broken down into the following activities: 1. Shielding and backscattering calculations for a POLLUX cask with spent fuel and a transfer cask with vitrified high level waste2. Design and construction of shielding casks which simulate a POLLUX cask and a transfer cask3. Planning of test programme with shielding casks4. Planning and design of instrumentation for experiment5. Execution of the measurements5.1 Above-ground measurements5.2 Underground measurements in the Asse mine6. Evaluation and documentation of the results. Dziedzina nauki engineering and technologyenvironmental engineeringenergy and fuels Program(-y) FP2-RADWASTOM 4C - Specific research and technical development programme (Euratom) in the field of management and storage of radioactive waste, 1990-1994 Temat(-y) B.1 - The underground facility in the Asse Salt Mine (FRG) Zaproszenie do składania wniosków Data not available System finansowania CSC - Cost-sharing contracts Koordynator Forschungszentrum Karlsruhe Technik und Umwelt GmbH Wkład UE Brak danych Adres Weberstraße 5 76133 Karlsruhe Niemcy Zobacz na mapie Koszt całkowity Brak danych Uczestnicy (2) Sortuj alfabetycznie Sortuj według wkładu UE Rozwiń wszystko Zwiń wszystko DEUTSCHE GESELLSCHAFT ZUM BAU UND BETRIEB VON ENDLAGERN FUER ABFALLSTOFFE MBH Niemcy Wkład UE Brak danych Adres Eschenstrasse 55 31201 PEINE Zobacz na mapie Koszt całkowity Brak danych NATIONAL RADIOACTIVE WASTE MANAGEMENT AGENCY OF FRANCE Francja Wkład UE Brak danych Adres Rue Jean Monnet 1-7 92298 CHATENAY MALABRY Zobacz na mapie Koszt całkowity Brak danych