Methods and Model Development for Coupled RELAP5/PARCS Analysis of the Atucha‐II Nuclear Power Plant
- 1. Nuclear Engineering and Radiological Sciences, University of Michigan, 2355 Bonisteel Boulevard, Ann Arbor, MI 48109, USA
- 2. Autoridad Regulatoria Nuclear, Avenida Del Libertador 8250, C1429BNP Buenos Aires, Argentina
Description
In order to analyze the steady state and transient behavior of CNA‐II, several tasks were required. Methods and models were developed in several areas. HELIOS lattice models were developed and benchmarked against WIMS/MCNP5 results generated by NA‐SA. Cross‐sections for the coupled RELAP5/PARCS calculation were extracted from HELIOS within the GenPMAXS framework. The validation of both HELIOS and PARCS was performed primarily by comparisons to WIMS/PUMA and MCNP for idealized models. Special methods were developed to model the control rods and boron injection systems of CNA‐II. The insertion of the rods is oblique, and a special routine was added to PARCS to treat this effect. CFD results combined with specialized mapping routines were used to model the boron injection system. In all cases there was good agreement in the results which provided confidence in the neutronics methods and modeling. A coupled code benchmark between U of M and U of Pisa is ongoing and results are still preliminary. Under a LOCA transient, the best estimate behavior of the core appears to be acceptable.
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Additional details
Identifiers
- DOI
- 10.1155/2011/759847;
Publishing Information
- Journal Title
- Science and Technology of Nuclear Installations
- Journal Volume
- 2011
- Journal Issue
- 1
- ISSN
- 1687-6075
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- A CODES; ATUCHA-2 REACTOR; BENCHMARKS; BORON; COMPUTERIZED SIMULATION; CONTROL ELEMENTS; FLUID MECHANICS; LOSS OF COOLANT; M CODES; NEUTRON PHYSICS; NUCLEAR POWER PLANTS; R CODES; REACTOR KINETICS; STEADY-STATE CONDITIONS; TRANSIENTS; VALIDATION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ELEMENTS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; KINETICS; MECHANICS; NATURAL URANIUM REACTORS; NUCLEAR FACILITIES; PHWR TYPE REACTORS; PHYSICS; POWER PLANTS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SEMIMETALS; SIMULATION; TESTING; THERMAL POWER PLANTS; THERMAL REACTORS
Optional Information
- Copyright
- © Author(s)
- Notes
- Record automatically processed