The effect of burn up on the kinetic parameters for a pressurized water reactor fueled by MOX using MCNPX code
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H. K. Louis
Abstract
Reactor kinetic parameters are very important for safety analysis in power reactors. This paper focused on calculations of kinetic parameters such as the effective delayed neutron fraction (βeff), the neutron generation time (Λ) and the prompt neutron lifetime lp for PWR. In this paper the burn-up calculations were performed to calculate kinetic parameters as a function of burn-up for a PWR when fueled with standard UO2 fuel and MOX (Mixed-Oxide) fuel in order to study the impact of burn-up on these parameters. The calculations were performed using the Monte Carlo code MCNPX. The core chosen for the simulation is based on a 4-loop Westinghouse PWR power plant. The calculations were performed from beginning of the life to the end of life 210 days and compared with safety values taken from the design control document of an AP1000 PWR. The results are in agreement for UO2 but not for MOX until end of cycle (EOC).
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© 2014, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Simulation of thermal fluid dynamics in parabolic trough receiver tubes with direct steam generation using the computer code ATHLET
- Measurement of velocity profiles of nanofluids in laminar channel flow using Particle Image Velocimetry
- Prediction of correlation between two-phase natural circulation flows in heated and unheated channels of a parallel channel system – based on electrical analogy
- Investigation of (n,γ) reactions in fissionable fluids in a hybrid reactor system
- In-pile modelling of nuclear fuel element for the MTR type reactors – Part 2
- One-step synthesis of Pt-reduced graphene oxide composites based on high-energy radiation technique
- Hamming generalized corrector for reactivity calculation
- Experimental study of flow inversion in MTR upward flow research reactors
- Technical Note
- The effect of burn up on the kinetic parameters for a pressurized water reactor fueled by MOX using MCNPX code
- Diffusion length calculations for one-speed neutrons in a slab with backward, forward and linear anisotropic scattering
- Improvement of passive shielding to reduce background components to determinate radioactivity at low energy gamma rays
- A study of the energy enhancement of electron in radio frequency (RF) linear accelerator of iris loaded waveguards
- Age-dependent effective doses for radionuclides uniformly distributed in air
