Burning of spent fuel of an accelerator-driven modular HTGR in sub-critical condition
- 1. Tsinghua Univ., Beijing (China). Inst. of Nuclear Energy Technology
Description
The modular high temperature gas cooled reactor (MHTGR) has good safety characteristics because of the use of coated particles in the fuel element. After the particles cool outside of the reactor for some time, the spent fuel can be re-utilized. The author describes a physics feasibility study for the burning of spent fuel from a 350 MW ring-shaped modular high temperature gas cooled reactor in an accelerator-driven sub-critical reactor. A conceptual design is given for the 30 MW accelerator-driven sub-critical reactor. The neutron transport in the sub-critical reactor was simulated using the MCNP code, and the burnup was calculated using the ORIGEN2 code. The results show that the accelerator-driven sub-critical gas-cooled reactor has reliable sub-criticality and low power density and that the spent fuel from a 350 MW ring-shaped modular high temperature gas cooled reactor can be burned to provide 20% more energy
Additional details
Publishing Information
- Journal Title
- Journal of Tsinghua University. Science and Technology
- Journal Volume
- 42
- Journal Issue
- 5
- Journal Page Range
- p. 646-647, 658
- ISSN
- 1000-0054
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 34019972
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ACCELERATOR FACILITIES; BREEDING RATIO; BURNUP; COMBUSTION; COMPUTERIZED SIMULATION; FEASIBILITY STUDIES; HTGR TYPE REACTORS; M CODES; MATHEMATICAL MODELS; MODULAR STRUCTURES; NEUTRON SPECTRA; NEUTRON TRANSPORT; O CODES; SPENT FUELS; SUBCRITICAL ASSEMBLIES
- Descriptors DEC
- CHEMICAL REACTIONS; COMPUTER CODES; CONVERSION RATIO; ENERGY SOURCES; EXPERIMENTAL REACTORS; FUELS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; MATERIALS; NEUTRAL-PARTICLE TRANSPORT; NUCLEAR FUELS; OXIDATION; RADIATION TRANSPORT; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION; SPECTRA; THERMOCHEMICAL PROCESSES