scholarly journals Polymeric seal degradation in nuclear power plants: Determination of physical and mechanical properties

2017 ◽  
Vol 135 (7) ◽  
pp. 45814 ◽  
Author(s):  
Christopher P. Porter ◽  
James P. Bezzina ◽  
Francis Clegg ◽  
Mark D. Ogden
Keyword(s):  
Mechanical Properties ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Physical And Mechanical Properties

scholarly journals Control Experiences Regarding Clearable Materials from Nuclear Power Plants and Nuclear Installations: Scaling Factors Determination and Measurements’ Acceptance Criteria Definition

Environments ◽  
2019 ◽  
Vol 6 (11) ◽  
pp. 120
Author(s):  
Luca Albertone ◽  
Massimo Altavilla ◽  
Manuela Marga ◽  
Laura Porzio ◽  
Giuseppe Tozzi ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Fission Products ◽  
Scaling Factors ◽  
Activation Products ◽  
Long Time ◽  
Nuclear Installation ◽  
Enriched Uranium

Arpa Piemonte has been carrying out, for a long time, controls on clearable materials from nuclear power plants to verify compliance with clearance levels set by ISIN (Ispettorato Nazionale per la Sicurezza Nucleare e la Radioprotezione - National Inspectorate for Nuclear Safety and Radiation Protection) in the technical prescriptions attached to the Ministerial Decree decommissioning authorization or into category A source authorization (higher level of associated risk, according to the categorization defined in the Italian Legislative Decree No. 230/95). After the experience undertaken at the “FN” (Fabbricazioni Nucleari) Bosco Marengo nuclear installation, some controls have been conducted at the Trino nuclear power plant “E. Fermi,” “LivaNova” nuclear installation based in Saluggia, and “EUREX” (Enriched Uranium Extraction) nuclear installation, also based in Saluggia, according to modalities that envisage, as a final control, the determination of γ-emitting radionuclides through in situ gamma spectrometry measurements. Clearance levels’ compliance verification should be performed for all radionuclides potentially present, including those that are not easily measurable (DTM, Difficult To Measure). It is therefore necessary to carry out upstream, based on a representative number of samples, those radionuclides’ determination in order to estimate scaling factors (SF), defined through the logarithmic average of the ratios between the i-th DTM radionuclide concentration and the related key nuclide. Specific radiochemistry is used for defining DTMs’ concentrations, such as Fe-55, Ni-59, Ni-63, Sr-90, Pu-238, and Pu-239/Pu-240. As a key nuclide, Co-60 was chosen for the activation products (Fe-55, Ni-59, Ni-63) and Cs-137 for fission products (Sr-90) and plutonium (Pu- 238, Pu-239/Pu-240, and Pu-241). The presence of very low radioactivity concentrations, often below the detection limits, can make it difficult to determine the related scaling factors. In this work, the results obtained and measurements’ acceptability criteria are presented, defined with ISIN, that can be used for confirming or excluding a radionuclide presence in the process of verifying clearance levels’ compliance. They are also exposed to evaluations regarding samples’ representativeness chosen for scaling factors’ assessment.

Radiochemical methodologies applied to determination of zirconium isotopes in low-level waste samples from nuclear power plants

2014 ◽  
Vol 302 (1) ◽  
pp. 41-47 ◽  
Author(s):  
T. C. Oliveira ◽  
R. P. G. Monteiro ◽  
G. F. Kastner ◽  
F. Bessueille-Barbier ◽  
A. H. Oliveira
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Low Level

Optimization of Concrete Container Composition in Radioactive Waste Management

1985 ◽  
Vol 50 ◽  
Author(s):  
I. B. Plecas ◽  
Li. L. Mihajlovic ◽  
A. M. Kostadinovic
Keyword(s):  
Mechanical Properties ◽  
Radioactive Waste ◽  
Waste Management ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Leakage Rate ◽  
Intermediate Level ◽  
Radioactive Waste Management ◽  
Intermediate Level Radioactive Waste

AbstractIn this paper an optimization of concrete container composition, used for storing low and intermediate level radioactive waste from nuclear power plants in Yugoslavia, is presented.Mechanical properties 37−52 MPa, permeability 1.07. 10−13 - 1.50. 10−11cm2 and leakage rate 3.66. 10−6 - 1.77. 10−4 cm/d for concrete made of commercial materials, were tested.

Structure and Mechanical Properties of Welded Joints for Nuclear Power Plants of Type MIR 1200

2017 ◽  
Vol 891 ◽  
pp. 201-205
Author(s):  
Ladislav Kander ◽  
Petr Čížek ◽  
Šárka Hermanová ◽  
Zdeněk Říha
Keyword(s):  
Mechanical Properties ◽  
Welded Joints ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Shear Fracture ◽  
Low Cycle Fatigue ◽  
Water Environment ◽  
Temperature Shift ◽  
Pressure Vessels

The paper deals with research, development and verification of production technology of selected welded joints for pressure vessels of primary circuits of nuclear power plants of type MIR 1200. Effect of various welding technology including simulation heat treatment on mechanical and fracture properties have been studied. Four type of homogenous 10GN2MFA – 10GN2MFA type of welded joints have been prepared for experimental programme. Conventional mechanical properties (tensile and impact test) as well as unconventional mechanical properties (fracture mechanics, low-cycle fatigue and stress corrosion cracking in water environment) have been studied. Effect of elevated working temperature on structure and material properties has been evaluated. Temperature dependencies of shear fracture have been plotted and effect of welding procedure on transition temperature shift has been evaluated. Experimental data have been compared with numerical simulation using FEM.

Diagnosis of hermetic zone of containment envelope of nuclear power plant on basis of control of geometry and mechanical properties of containment

2020 ◽  
pp. 195-199
Author(s):  
V.V. Potapov ◽  
V.A. Il’in
Keyword(s):  
Mechanical Properties ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Laser Scanning ◽  
Nuclear Power Plants ◽  
Thickness Measurement ◽  
The State

The features for application of laser scanning of the lining geometry, the thickness measurement of the lining and the measurement of hardness with the subsequent assessment of mechanical properties to monitor the state of the pressurized volume of the containment envelope of nuclear power plants with VVER are considered.

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