会议专题

A High Fidelity JTopmeret? Model for Gas-Cooled Reactors

The Jtopmeret? Two-phase thermal-hydraulic code has been widely used to provide high fidelity Balance-of-Plant (BOP) real-time simulator models for conventional Nuclear and Fossil reactors. Recently, several models essential to simulate components of gas reactors were developed and integrated within Jtopmeret?. These models include gas transport medium (Helium and CO2,with real gas thermodynamic properties), large scale gas power turbine and gas compressor (blower), heat exchangers (recuperators and coolers), and a three-dimensional graphite core structure interspersed with gas coolant flows. These models have been presented in earlier papers 1,2,3. This paper shall provide an overview of the models, and demonstrate full modeling capabilities for two major reactor types. One is a conventional Advanced Gas Reactors (AGR), which employs CO2 as the coolant. The other one is a First of a Kind Engineering (FOAKE) PBMR, which uses Helium as the coolant. Both AGR and PBMR have complicated heat structure material in the core as moderators. The discussions include two PBMR design variations: a Demonstration Power Plant at 400 MWth (DPP400) and a Steam Power Cycle System (SPCS) 4 at 250 MWth. The SPCS as described here represents a class of options. Final design parameters and layout of the SPCS system is still under design. The revised Jtopmeret? 5 can be used as an engineering grade Thermal-hydraulic model for full scope gas cooled reactors.

JTopmeret Thermal Hydraulic Gas Reactors PBMR AGR

Zen Wang Y.C. Lee Evgeny Grachev Robert Luh Frik Geyser Piet De Villiers

GSE Systems, Inc. 1332 Londontown Blvd, Sykesville, MD 21784, USA GSE Systems, Inc.1332 Londontown Blvd, Sykesville, MD 21784, USA PBMR Pty (Ltd.)1279 Mike Crawford Avenue, Centurion, 0046, South Africa

国际会议

The 8th International Topical Meeting on Nuclear Thermal-Hydraulics,Operation and Safety(第八届反应堆热工水力、运行和安全国际会议 NUTHOS-8)

上海

英文

1909-1920

2010-10-10(万方平台首次上网日期,不代表论文的发表时间)