V and V of the HTR Code Package (HCP) as a comprehensive HTR steady state and transient safety analysis framework - 18664
- Juelich, Forschungszentrum 52425 Juelich, Germany (Germany)
The HTR code package (HCP) allows for the simulation of several safety-related aspects of a High Temperature Reactor core in a highly integrated manner. HCP currently couples the thermo-fluid dynamics and time dependent neutronics code MGT, the spectrum code TRISHA, the burn up code TNT, the fuel management code SHUFLE and the fission product release code STACY. During its development, state-of-the-art programming techniques and standards are applied. The cross sections in HCP are generated by a 0D- or 1D solver featuring an innovative approach to treat the double heterogeneity of pebble fuel. Also major improvements have been made to optimize the nuclear data library based on ENDF/B-VII. Two advanced fuel management models are provided by the code module SHUFLE that go far beyond the capabilities of existing system codes like VSOP. The source term analysis code module STACY is coupled to HCP providing release rate calculations with a high spatial resolution making use of the nuclide densities provided by TNT. An outstanding new feature of HCP is the possibility to simulate long-term operation scenarios based on OTTO or MEDUL fuel shuffling schemes as well as selected transients in one integrated code package. Even alternating steady state/transient/steady state simulations are possible. So with HCP different fuel strategies and their influence on various kinds of accidents can be examined with one consistent reactor model. This paper provides an overview of the development status of the HCP and reports about selected benchmark results. It is demonstrated that the new system code HCP is capable to replace existing stand-alone codes like VSOP, TINTE/MGT, FRESCO or PANAMA while introducing new features, which so far to our knowledge were not available in the field of HTR safety research. (authors)
- Research Organization:
- American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 23032724
- Resource Relation:
- Conference: HTR 2016: International Topical Meeting on High Temperature Reactor Technology, Las Vegas, NV (United States), 6-10 Nov 2016; Other Information: Country of input: France; 26 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BENCHMARKS
BURNUP
COMPUTERIZED SIMULATION
CROSS SECTIONS
FISSION PRODUCT RELEASE
FLUID MECHANICS
FUEL MANAGEMENT
HTGR TYPE REACTORS
NUCLEAR DATA COLLECTIONS
NUCLEAR FUELS
REACTOR ACCIDENTS
REACTOR CORES
REACTOR OPERATION
SAFETY ANALYSIS
SOURCE TERMS
SPATIAL RESOLUTION
STEADY-STATE CONDITIONS
TIME DEPENDENCE
TRANSIENTS