Implications of Graphite Radiation Damage on the Neutronic, Operational, and Safety Aspects of Very High Temperature Reactors
In both the prismatic and pebble bed designs of Very High Temperature Reactors (VHTR), the graphite moderator is expected to reach exposure levels of 1021 to 1022 n/cm2 over the lifetime of the reactor. This exposure results in damage to the graphite structure. In this work, molecular dynamic and ab initio molecular static calculations will be used to: 1) simulate radiation damage in graphite under various irradiation and temperature conditions, 2) generate the thermal neutron scattering cross sections for damaged graphite, and 3) examine the resulting microstructure to identify damage formations that may produce the high-temperature Wigner effect. The impact of damage on the neutronic, operational and safety behavior of the reactor will be assessed using reactor physics calculations. In addition, tests will be performed on irradiated graphite samples to search for the high-temperature Wigner effect, and phonon density of states measurements will be conducted to quantify the effect on thermal neutron scattering cross sections using these samples.
- Research Organization:
- North Carolina State Univ., Raleigh, NC (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- FC07-07ID14818
- OSTI ID:
- 1025722
- Report Number(s):
- DOE.ID.ID14818; TRN: US201120%%736
- Country of Publication:
- United States
- Language:
- English
Similar Records
Thermal Hydraulics of the Very High Temperature Gas Cooled Reactor
Next Generation Nuclear Plant Research and Development Program Plan