Enhanced Density Materials at Nuclear Power Facilities

#2771

Development and Study of Properties of Enhanced Density Composite Materials for Construction Activities at Nuclear Power Facilities

Tech Area / Field

MAT-COM/Composites/Materials

Status
3 Approved without Funding

Registration date
15.05.2003

Leading Institute
VNIITF, Russia, Chelyabinsk reg., Snezhinsk

Supporting institutes

FIAN Lebedev, Russia, Moscow\nPenza State Academy for Architecture and Construction, Russia, Penza reg., Penza

Collaborators

Eurotech Ltd., USA, VA, Fairfax\nUniversitat Leipzig / Institute fuer Massivbau und Baustofftechnologie, Germany, Leipzig

Project summary

The main objective of the project is improvement of a composition and more accurate specification of properties of enhanced-density composite materials (EDCM) of essentially improved constructional characteristics and level of ionizing radiation protection. It is proposed to use these materials for construction of nuclear power facilities at NPP, for radioactive wastes storing, for localization of radioactive contamination in the case of radiation accidents, biological shielding at radiation-dangerous Facilities, and consolidation of potentially hazardous wastes (spent uranium mines and their refuse heaps). If an application requires, the material composition can be corrected to provide the required factors of average and real densities, impenetrability, and life duration. The project will investigate the basic factors, which determine the radiation-protective and structural properties of developed composite materials, for operation under condition of ionizing radiation exposure as well as for fabrication frame structures for hoppers, depositories, and RW storage facilities.

The main research directions are the following:

- improvement of a composition and research of physical-mechanical and operational properties of EDCM;

- mathematical simulation of protective properties of EDCM;
- research of radiation-protective properties of enhanced-density composite materials in relation to the type of ionizing radiation, its energy, as well as the value of absorbed dose.

Samples will be manufactured to meet the requirements for application in construction of nuclear engineering facilities. The samples will be characterized by the following properties:

- Average density, kg/m³ 5500 ... 7500

- Pressure breaking point, MPa 15 ... 45
- Porosity, % 4 ... 10
- Water absorbing, % 0.06 ... 1.4
- Steel reinforcement bond resistance, MPa 1.9 ... 4.1
- Frost-resistance, cycles: > 200 ... 250
- Chemical resistance coefficient in acid, alkaline and salt solutions: 0.9 ... 1
- Radiation resistance coefficient: 0.9 ... 0.95
- Linear attenuation constant for gamma radiation > 0.3 cm^-1

The work is over with testing of the developed materials by collaborators and issuing recommendations to application and to an industrial production.

The commercial importance of the project resides in development and creation of previously unknown enhanced-density composite materials with characteristics providing them wide application in atomic power engineering, technology, and ecology.

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