Published March 2012 | Version v1
Miscellaneous Metadata-only

Thermal conductivity of nuclear oxide fuel under temperature gradient. Molecular dynamics simulation

Creators

  • 1. Kyushu Univ., Graduate School of Engineering, Fukuoka (Japan)
  • 2. Japan Atomic Energy Agency, Nuclear Fuel Cycle Engineering Laboratories, Tokai, Ibaraki (Japan)

Description

Thermal conductivities of UO2, PuO2 and (U0.8, Pu0.2) O2-x (x=0.02-0.1) under the temperature gradient were derived and evaluated by means of non-equilibrium molecular dynamics simulations (NEMD). NEMD results qualitatively showed the decrease of the thermal conductivity due to phonon-phonon and phonon-impurities interaction. Meanwhile, it was found that the thermal conductivity was affected by the length of the supercell. (author)

Part of:
1st Asian nuclear fuel conference (ANFC 2012)

Additional details

Publishing Information

Imprint Title
1st Asian nuclear fuel conference (ANFC 2012)
Imprint Pagination
112 p.
Journal Page Range
p. 26-27

Conference

Title
1. Asian nuclear fuel conference
Acronym
ANFC 2012
Dates
22-23 Mar 2012
Place
Osaka (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
46114611
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTERIZED SIMULATION; M CODES; MIXED OXIDE FUELS; MOLECULAR DYNAMICS METHOD; MOMENTUM TRANSFER; PHONONS; PLUTONIUM DIOXIDE; REACTOR SAFETY; TEMPERATURE DEPENDENCE; TEMPERATURE GRADIENTS; THERMAL CONDUCTIVITY; URANIUM DIOXIDE
Descriptors DEC
ACTINIDE COMPOUNDS; CALCULATION METHODS; CHALCOGENIDES; COMPUTER CODES; ENERGY SOURCES; FUELS; MATERIALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; PLUTONIUM COMPOUNDS; PLUTONIUM OXIDES; QUASI PARTICLES; REACTOR MATERIALS; SAFETY; SIMULATION; SOLID FUELS; THERMODYNAMIC PROPERTIES; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES

Optional Information

Notes
5 refs., 5 figs.