A point kinetics model for dynamic simulations of next generation nuclear reactor
| Autor: | Jean-Michel Tournier, Mohamed S. El-Genk |
|---|---|
| Rok vydání: | 2016 |
| Předmět: |
Materials science
InHour Next Generation Nuclear Plant 020209 energy Nuclear engineering Energy Engineering and Power Technology Continuous stirred-tank reactor 02 engineering and technology Nuclear reactor Very-high-temperature reactor law.invention Dynamic simulation Nuclear Energy and Engineering law 0202 electrical engineering electronic engineering information engineering Transient response Safety Risk Reliability and Quality Plug flow reactor model Waste Management and Disposal |
| Zdroj: | Progress in Nuclear Energy. 92:91-103 |
| ISSN: | 0149-1970 |
| DOI: | 10.1016/j.pnucene.2016.07.007 |
| Popis: | An accurate, fast-running and stable six-group, point kinetics (PK) model is developed and applied successfully to the dynamic simulation of the operation of the prismatic core, high temperature next generation nuclear plant (NGNP) reactor. The model is unrestricted by the size of the time step, which could be as much as several seconds, accounts for Doppler Broadening and the fuel and graphite temperature reactivity feedbacks, and includes an active neutron source for zero-power reactor startup. An efficient and robust numerical technique that approximates the exponential matrix using 7th order-accurate Pade(3,3) function with a discretization error on the order of (Δt)3, solves the coupled nonlinear and stiff six-groups point kinetics equations. The PK model handles reactivity insertions in excess of a prompt critical, ρ / β ¯ > $1.0, with unrestrictive time step size. Model results are successfully benchmarked using the Inhour solution for a step insertion of external reactivity. To simulate the transient response of the NGNP reactor following an external reactivity insertion and during a startup, the PK model is coupled to 84-nodes thermal-hydraulics model of the reactor, also developed in this work. With a 2 s time step, the error of predicting the reactor thermal power is ∼0.001%, increasing exponentially to ∼0.08% and ∼1.5% with increased time step size to 5 and 8 s, respectively. The present PK model has been successfully incorporated into MELCOR-H2 nuclear reactor analysis code to simulate transient operation of Very High Temperature Reactor (VHTR) for electricity generation, using a Closed Brayton Cycle turbomachinery, and the co-generation of hydrogen using Sulfur Iodine (SI) thermochemical processes. |
| Databáze: | OpenAIRE |
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