Development of a Non-Destructive Gamma Spectrometry Technique for Optimization of Metallic Waste Characterization
Creators
- 1. National Center of Scientific Research "Demokritos", Institute of Nuclear and Radiological Sciences and Technology, Energy and Safety, Radioactive Waste and Material Laboratory, Athens (Greece)
- 2. Aristotle University of Thessaloniki (Greece)
Description
Adequate radiological characterization is important for optimization of metallic waste management. For decommissioning planning, the objective is to obtain a radiological understanding of the involved installation. The characterization at this stage could be carried out by means of: 1) neutron activation calculations based on reactor design and neutron flux; 2) dose rate measurements; 3) in-situ gamma spectrometry; 4) sampling for determination of the scaling factors in activated and contaminated components. During dismantling, in-situ characterization is carried out to classify and package the generated waste. This is usually achieved by using portable devices to measure dose rates or total counts. Then, the packages are monitored for assessment of activity and determination of the management route. The radiological characterization of activated components, which appeared with surface contamination, is essential for the decision making process during decommissioning. The selection of cutting and decontamination techniques should be based on accurate determination of the radionuclides inside the material and/ or on the surface contamination. Also, after dismantling, the metallic waste may be activated and/or contaminated with radionuclides which are products of neutron activation or fission. It is important to decide in which cases the decontamination will be efficient as well as to select the appropriate decontamination techniques based on whether the waste is slightly activated or contaminated or both. Α Semiempirical technique for optimization of determination of contamination and activation of components and metallic waste is under development based on combination of gamma spectrometry measurements and MCNPX Monte Carlo simulations. Firstly, the technique aims at reduction of the uncertainties related to the density and activity distribution. The specific activities inside and on the surface of the materials could be determined by using the measurement results of the proposed non-destructive technique in combination with the use of the scaling factors for activation and/ or contamination. (author)
Additional details
Identifiers
Publishing Information
- Imprint Title
- International Conference on Radioactive Waste Management: Solutions for a Sustainable Future. Book of Abstracts
- Imprint Pagination
- 247 p.
- Journal Page Range
- p. 74
- Report number
- IAEA-CN--294
Conference
- Title
- Solutions for a Sustainable Future
- Acronym
- International Conference on Radioactive Waste Management
- Dates
- 1-5 Nov 2021
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 53084412
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; DECOMMISSIONING; DECONTAMINATION; DENSITY; DOSE RATES; FISSION; GAMMA SPECTROSCOPY; MATERIALS; MONTE CARLO METHOD; NEUTRON FLUX; NEUTRONS; OPTIMIZATION; RADIOACTIVE WASTE MANAGEMENT; RADIOISOTOPES; REACTOR DESIGN; SAMPLING; SCALING; SURFACE CONTAMINATION; SURFACES
- Descriptors DEC
- BARYONS; CALCULATION METHODS; CLEANING; CONTAMINATION; DESIGN; ELEMENTARY PARTICLES; FERMIONS; HADRONS; ISOTOPES; MANAGEMENT; NUCLEAR REACTIONS; NUCLEONS; PHYSICAL PROPERTIES; RADIATION FLUX; REACTOR LIFE CYCLE; SIMULATION; SPECTROSCOPY; WASTE MANAGEMENT
Optional Information
- Secondary number(s)
- IAEA-CN--294-208