Analysis of the Peach Bottom flow stability test number 3 using the coupled RELAP5/PARCS code

Salah, A Bousbia; D'Auria, Francesco Saverio

doi:10.1016/j.anucene.2006.02.012

Cited by 7 publications

(1 citation statement)

References 5 publications

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“…Typically, the system dynamics of a reactor is simulated by the complex codes consisting of the one-dimensional or three-dimensional neutronics, the correlations of two-phase follow, critical flow and thermal properties, and the built in control system blocks. Those codes such as RELAP, RETRAN, and TRACE, are applied for safety analyses, plant design, and predictions of postulated tests [1,2,3]. Although those advanced codes are programmed to calculate the systematic parameters during significant transients, the computing time is proportional to the nodolization of reactor models and specific transients.…”

Section: Introductionmentioning

confidence: 99%

Construction of an Elementary Model for the Dynamic Analysis of a Pressurized Water Reactor

Tsai

Shih

Wang

2013

AMM

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A lumped-parameter numerical model was constructed based on the conservation laws of mass and energy and the point neutron kinetics with 6 groups of delayed neutron to represent the dynamics of primary loop of a pressurized water reactor (PWR) core. On the viewpoint of control theory, the coupled phenomenon of neutron kinetics and thermohydraulics can be recognized as a dynamic system with feedback loops which is caused by the Doppler effect and the coolant temperature difference. Scilab was implemented to representing the equivalent transfer functions and associated feedback loops of a PWR core. The dynamic responses were performed by the perturbations of coolant inlet flow, coolant inlet temperature, and reactivity insertion.

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Section: Introductionmentioning

confidence: 99%