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Radiological Characterization and Application of Release Criteria
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Proceedings Papers

Gamma Spectrometry Measurement for the Soil in Contaminated Fields

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Zhiwei Cheng
Proc. ASME. ICEM2001, Volume 2: Mgmt. Low/Interm. Level Waste; Spent Fuel; Economics/Analyses for Waste Mgmt.; Radiological Characterization/Application Release Criteria; Panel Sessions; Solid Waste Reduction/Treatment; Current Activities in Central/Eastern Europe; Environmental Remediation Technology; LL/ILW; HLW/Spent Fuel; Chernobyl; D&D Waste; Performance Assessment; MOX and Spent UOX; D&D Nuclear Reactors; Decommissioning of Other Nuclear Facilities, 811-812, September 30–October 4, 2001
Publisher: American Society of Mechanical Engineers
Paper No: ICEM2001-1144
https://doi.org/10.1115/ICEM2001-1144
View Paper titled, Gamma Spectrometry Measurement for the Soil in Contaminated Fields
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Topics: Gamma ray spectrometry, Soil
Proceedings Papers

Dismantling of a Nuclear Fuel Fabric - Release of Building Rubble and Site: An Overview

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Elisabeth T. Aberl, Karl-Heinz Lehmann
Proc. ASME. ICEM2001, Volume 2: Mgmt. Low/Interm. Level Waste; Spent Fuel; Economics/Analyses for Waste Mgmt.; Radiological Characterization/Application Release Criteria; Panel Sessions; Solid Waste Reduction/Treatment; Current Activities in Central/Eastern Europe; Environmental Remediation Technology; LL/ILW; HLW/Spent Fuel; Chernobyl; D&D Waste; Performance Assessment; MOX and Spent UOX; D&D Nuclear Reactors; Decommissioning of Other Nuclear Facilities, 791-794, September 30–October 4, 2001
Publisher: American Society of Mechanical Engineers
Paper No: ICEM2001-1141
https://doi.org/10.1115/ICEM2001-1141
View Paper titled, Dismantling of a Nuclear Fuel Fabric - Release of Building Rubble and Site: An Overview
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Topics: Nuclear fuels, Textiles, Sanitary landfills, Decontamination, Fuel rods, Soil, Structures, Uranium
Proceedings Papers

Characterisations and Measurements for Free Release: An Overview of the Studsvik Experiences

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Maria Lindberg, Börje Johnsson
Proc. ASME. ICEM2001, Volume 2: Mgmt. Low/Interm. Level Waste; Spent Fuel; Economics/Analyses for Waste Mgmt.; Radiological Characterization/Application Release Criteria; Panel Sessions; Solid Waste Reduction/Treatment; Current Activities in Central/Eastern Europe; Environmental Remediation Technology; LL/ILW; HLW/Spent Fuel; Chernobyl; D&D Waste; Performance Assessment; MOX and Spent UOX; D&D Nuclear Reactors; Decommissioning of Other Nuclear Facilities, 771-774, September 30–October 4, 2001
Publisher: American Society of Mechanical Engineers
Paper No: ICEM2001-1137
https://doi.org/10.1115/ICEM2001-1137
View Paper titled, Characterisations and Measurements for Free Release: An Overview of the Studsvik Experiences
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Topics: Anterior cruciate ligament, Boilers, Decontamination, Heavy water reactors, Melting, Metals, Nuclear decommissioning, Nuclear industry, Nuclear power stations, Scrap metals
Proceedings Papers

Concrete Crushing and Sampling, a Methodology and Technology for the Unconditional Release of Concrete Material From Decommissioning

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Sven Baumann, Lucien Teunckens, Robert Walthéry, Patrick Lewandowski, Danny Millen
Proc. ASME. ICEM2001, Volume 2: Mgmt. Low/Interm. Level Waste; Spent Fuel; Economics/Analyses for Waste Mgmt.; Radiological Characterization/Application Release Criteria; Panel Sessions; Solid Waste Reduction/Treatment; Current Activities in Central/Eastern Europe; Environmental Remediation Technology; LL/ILW; HLW/Spent Fuel; Chernobyl; D&D Waste; Performance Assessment; MOX and Spent UOX; D&D Nuclear Reactors; Decommissioning of Other Nuclear Facilities, 775-780, September 30–October 4, 2001
Publisher: American Society of Mechanical Engineers
Paper No: ICEM2001-1138
https://doi.org/10.1115/ICEM2001-1138
View Paper titled, Concrete Crushing and Sampling, a Methodology and Technology for the Unconditional Release of Concrete Material From Decommissioning
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Topics: Concretes, Nuclear decommissioning, Structures, Demolition, Storage, Clearances (Engineering), Decontamination, Industrial wastes, Metals, Particulate matter
Proceedings Papers

Radiological Characterization of Steel Scrap Recycling by Melting

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Ulrich Quade
Proc. ASME. ICEM2001, Volume 2: Mgmt. Low/Interm. Level Waste; Spent Fuel; Economics/Analyses for Waste Mgmt.; Radiological Characterization/Application Release Criteria; Panel Sessions; Solid Waste Reduction/Treatment; Current Activities in Central/Eastern Europe; Environmental Remediation Technology; LL/ILW; HLW/Spent Fuel; Chernobyl; D&D Waste; Performance Assessment; MOX and Spent UOX; D&D Nuclear Reactors; Decommissioning of Other Nuclear Facilities, 781-784, September 30–October 4, 2001
Publisher: American Society of Mechanical Engineers
Paper No: ICEM2001-1139
https://doi.org/10.1115/ICEM2001-1139
View Paper titled, Radiological Characterization of Steel Scrap Recycling by Melting
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Topics: Melting, Radiological characterization, Recycling, Steel, Metals, Containers, Decontamination, Dust, Filters, Nuclides
Proceedings Papers

Finding, Identifying, Localizing, and Quantifying Hidden Radioactivity Using Non-Invasive InSitu Gamma Spectroscopy

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Frazier L. Bronson
Proc. ASME. ICEM2001, Volume 2: Mgmt. Low/Interm. Level Waste; Spent Fuel; Economics/Analyses for Waste Mgmt.; Radiological Characterization/Application Release Criteria; Panel Sessions; Solid Waste Reduction/Treatment; Current Activities in Central/Eastern Europe; Environmental Remediation Technology; LL/ILW; HLW/Spent Fuel; Chernobyl; D&D Waste; Performance Assessment; MOX and Spent UOX; D&D Nuclear Reactors; Decommissioning of Other Nuclear Facilities, 785-790, September 30–October 4, 2001
Publisher: American Society of Mechanical Engineers
Paper No: ICEM2001-1140
https://doi.org/10.1115/ICEM2001-1140
View Paper titled, Finding, Identifying, Localizing, and Quantifying Hidden Radioactivity Using Non-Invasive InSitu Gamma Spectroscopy
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Topics: Gamma ray spectrometry, Radioactivity, Concretes, Radiological characterization, Calibration, Ceilings, Containers, Neutrons, Nuclides, Radioisotopes
Proceedings Papers

Experimental Study on Radioactive Contamination of Spent Reactor Graphite From the SGCE (Tomsk-7) Plutonium-Production Reactors

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Anatoly Bushuev, Yury Verzilov, Victor Zubarev, Tatiana Aleeva, Ekaterina Petrova, Igor Proshin, Alexander Kachanovsky, Boris Silin, Alexander Dmitriev, Elena Zakharova, Sergey Ushakov, Andrey Nikolaev, Igor Baranov, Yury Kabanov, Ella Kolobova
Proc. ASME. ICEM2001, Volume 2: Mgmt. Low/Interm. Level Waste; Spent Fuel; Economics/Analyses for Waste Mgmt.; Radiological Characterization/Application Release Criteria; Panel Sessions; Solid Waste Reduction/Treatment; Current Activities in Central/Eastern Europe; Environmental Remediation Technology; LL/ILW; HLW/Spent Fuel; Chernobyl; D&D Waste; Performance Assessment; MOX and Spent UOX; D&D Nuclear Reactors; Decommissioning of Other Nuclear Facilities, 795-801, September 30–October 4, 2001
Publisher: American Society of Mechanical Engineers
Paper No: ICEM2001-1142
https://doi.org/10.1115/ICEM2001-1142
View Paper titled, Experimental Study on Radioactive Contamination of Spent Reactor Graphite From the SGCE (Tomsk-7) Plutonium-Production Reactors
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Topics: Contamination, Graphite, Radioisotopes, Irradiation (Radiation exposure), Neutrons, Nuclear fission, X-ray spectroscopy
Proceedings Papers

Keeping the Clearance Levels of NPP Building Structures Validation by Measurement of the Nuclide-Specific Dose-Rate

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Lothar Hummel
Proc. ASME. ICEM2001, Volume 2: Mgmt. Low/Interm. Level Waste; Spent Fuel; Economics/Analyses for Waste Mgmt.; Radiological Characterization/Application Release Criteria; Panel Sessions; Solid Waste Reduction/Treatment; Current Activities in Central/Eastern Europe; Environmental Remediation Technology; LL/ILW; HLW/Spent Fuel; Chernobyl; D&D Waste; Performance Assessment; MOX and Spent UOX; D&D Nuclear Reactors; Decommissioning of Other Nuclear Facilities, 803-809, September 30–October 4, 2001
Publisher: American Society of Mechanical Engineers
Paper No: ICEM2001-1143
https://doi.org/10.1115/ICEM2001-1143
View Paper titled, Keeping the Clearance Levels of NPP Building Structures Validation by Measurement of the Nuclide-Specific Dose-Rate
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Topics: Clearances (Engineering), Nuclear power stations, Nuclides, Germanium, Nuclear decommissioning, Sensors, Spectroscopy, Structures