Dismantling and decommissioning: The interest of passive neutron measurement to control and characterise radioactive wastes containing uranium
Creators
- 1. Commissariat à l'Energie Atomique, CEA Cadarache (France)
- 2. AREVA NC, UPA/EMP, BP16, 26701 Pierrelatte cedex (France)
Description
Highlights: ► Application of passive neutron measurement the SOURCES4C code and the MCNP4C2 Monte Carlo code Detection Limit Mass (DLM) of less than a few grams of 235U one thousand compressors have to be industrially measured. - Abstract: This paper deals with the evacuation of the wastes resulting from the dismantling of an 235U enrichment facility. Gamma-ray spectrometry is usually used to quantify the 235U residual mass and the activity of those wastes. In the present case, the waste internal content made of aluminium prevents gamma-rays from reaching the detector. We show here how neutron passive measurement has been used as an alternative to gamma-ray spectrometry. The controlled objects are about 1000 compressors of masses up to 2000 kg employed in a gaseous diffusion enrichment process. A dedicated neutron-based setup has been designed using Monte Carlo modelling, and a Detection Limit Mass (DLM) of about 4–6 g of 235U is reached. For one of the compressors, the 235U measured mass has been compared to the same mass determined by destructive methods. The comparison shows a very good agreement.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nimb.2011.09.018Additional details
Identifiers
- DOI
- 10.1016/j.nimb.2011.09.018;
- PII
- S0168-583X(11)00882-2;
Publishing Information
- Journal Title
- Nuclear Instruments and Methods in Physics Research. Section B, Beam Interactions with Materials and Atoms
- Journal Volume
- 271
- Journal Issue
- Complete
- Journal Page Range
- p. 48-54
- ISSN
- 0168-583X
- CODEN
- NIMBEU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 43106273
- Subject category
- S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- ALUMINIUM; COMPUTERIZED SIMULATION; CONTROL; GAMMA SPECTROSCOPY; GASEOUS DIFFUSION; ISOTOPE SEPARATION PLANTS; MONTE CARLO METHOD; NEUTRON DETECTION; RADIOACTIVE WASTES; REACTOR DECOMMISSIONING; REACTOR DISMANTLING; SENSITIVITY; URANIUM 235
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; CALCULATION METHODS; DECOMMISSIONING; DEMOLITION; DETECTION; DIFFUSION; ELEMENTS; EVEN-ODD NUCLEI; HEAVY NUCLEI; INDUSTRIAL PLANTS; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MATERIALS; METALS; MINUTES LIVING RADIOISOTOPES; NUCLEAR FACILITIES; NUCLEI; RADIATION DETECTION; RADIOACTIVE MATERIALS; RADIOISOTOPES; SIMULATION; SPECTROSCOPY; SPONTANEOUS FISSION RADIOISOTOPES; URANIUM ISOTOPES; WASTES; YEARS LIVING RADIOISOTOPES
Optional Information
- Copyright
- Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.