Thermomechanics challenges in new nuclear reactor technologies
Creators
- 1. Universidad Autonoma Metropolitana, Unidad Iztapalapa, Area de Ingenieria en Recursos Energeticos, 09340 Ciudad de Mexico (Mexico)
- 2. Royal Institute of Technology - KTH, 114-28 Stockholm (Sweden)
Description
The extreme operation conditions, such as higher temperature and pressure, higher neutronic flow, higher levels of burn-up, swelling, and irradiation in the cladding in the new technologies of nuclear reactors, generate more advanced thermomechanics analysis and new methodologies to study the heterogenic of the core and the porous media in fuel pellets. Further, the long operation and extended operation licenses of Nuclear Power Plants (NPP) generate a necessity to consider thermomechanics phenomena in the analysis and design of nuclear reactors. This paper reviews some of the fuels and structural materials used in advanced nuclear reactors, also some techniques to ensure fuel safety for accident conditions, such as a coated fuel cladding Accident Tolerant Fuel (Atf). These methodologies include the Volume Average Method (VAM), which considers the porosity and contact surface between different phases in the fuel rod in the core of the nuclear reactor. Also, an analytical module to analyze the fuel pellet with and without gap has been developed to evaluate the mechanical behaviors of the Atf cladding, and the main results are presented, using values of Young Modulus and Poisson ratio in function of temperature. (author)
Files
54034690.pdf
Files
(1.5 MB)
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Additional details
Publishing Information
- Publisher
- Sociedad Nuclear Mexicana
- Imprint Place
- Ciudad de Mexico (Mexico)
- Imprint Pagination
- 13 p.
- Report number
- INIS-MX--3661
Conference
- Title
- nuclear power, the most efficient energy source to mitigate global warming
- Original Conference Title
- 33. Congreso Anual de la SNM: energia nuclear, la fuente de energia mas eficiente para mitigar el calentamiento global
- Acronym
- 33. SNM Annual Congress
- Dates
- 13-16 Nov 2022
- Place
- Veracruz, Ver. (Mexico)
INIS
- Country of Publication
- Mexico
- Country of Input or Organization
- Mexico
- INIS RN
- 54034690
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENT-TOLERANT NUCLEAR FUELS; BURNUP; CLADDING; DATA; FUEL PELLETS; FUEL RODS; IRRADIATION; LICENSES; NEUTRON TRANSPORT; NUCLEAR POWER PLANTS; POISSON RATIO; POROSITY; REACTOR OPERATION; REACTOR SAFETY; REACTOR TECHNOLOGY; REACTORS; SWELLING; TEMPERATURE DEPENDENCE; TEMPERATURE RANGE 0400-1000 K; YOUNG MODULUS
- Descriptors DEC
- DEFORMATION; DEPOSITION; DIMENSIONLESS NUMBERS; ENERGY SOURCES; FUEL ELEMENTS; FUELS; INFORMATION; MATERIALS; MECHANICAL PROPERTIES; NEUTRAL-PARTICLE TRANSPORT; NUCLEAR FACILITIES; NUCLEAR FUELS; OPERATION; PELLETS; POWER PLANTS; RADIATION TRANSPORT; REACTOR COMPONENTS; REACTOR LIFE CYCLE; REACTOR MATERIALS; SAFETY; SURFACE COATING; TEMPERATURE RANGE; THERMAL POWER PLANTS