Coupled neutronic thermo-hydraulic analysis of full PWR core with BGCore system
Coupled neutronic thermo-hydraulic analysis of full PWR core with BGCore system
Kotlyar, D.; Fridman, E.; Shwageraus, E.
Abstract
BGCore reactor analysis system, recently developed at Ben-Gurion University for calculating in-core fuel composition and spent fuel emissions following discharge, couples the Monte Carlo neutronic code (MCNP4C) with an independently developed burnup and decay module SARAF. The BGCore utilizes multi-group approach for generation of one group cross-sections. According to this approach, only multi-group neutron spectrum is calculated by MCNP, while reaction rates are calculated in a separate subroutine using pre-generated multi-group cross-section set and the fine group neutron spectrum obtained from MCNP.
BGCore code system offers a number of advantages over similar MCNP-depletion codes. These include:
- Multi-group coupling approach significantly reduces the code execution time without compromising the accuracy of the results.
- Use of the most recent data based on JEFF-3.1 data files,
- Careful choice of about 1700 isotopes to cover all potentially significant aspects of fuel irradiation and decay. All nuclides are included in the calculation matrix with no asymptotic approximation,
- The fact that all of the isotopes, and not just the most neutronically important, are tracked in the BGCore throughout all depletion steps, allows calculations of post-irradiation fuel characteristics such as, activity, radiotoxicity, and decay heat with high degree of accuracy.
This study presents the results of coupled neutronic T-H analysis of full PWR core performed with BGCore system. The verification of BGCore system results against alternative state of the art computer code is also presented.
Keywords: Monte-Carlo burnup; coupled neutronic thermal-hydraulic analysis
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Beitrag zu Proceedings
Jahrestagung Kerntechnik 2009, 12.-14.05.2009, Dresden, Deutschland -
Vortrag (Konferenzbeitrag)
Jahrestagung Kerntechnik 2009, 12.-14.05.2009, Dresden, Deutschland
Permalink: https://www.hzdr.de/publications/Publ-12047