Spatial instability analysis in pressurized water reactors

Obaidurrahman, K.; Doshi, J. B.

doi:10.1016/j.anucene.2010.10.015

Cited by 22 publications

(4 citation statements)

References 14 publications

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“…where ν is fission neutron multiplicity, and X 0 is the reference (steady-state) 135 Xe concentration. Space-time oscillations of the 135 Xe concentration, imprecisely also referred to simply as "xenon oscillations", are a well-known phenomenon which might also occur during or after other, nonload-following, transients (Gyorey, 1962;Lellouche, 1962;Randall and John, 1962;Shotkin and Abernathy, 1963;Christie and Poncelet, 1973;Bauer and Poncelet, 1974;El-Bassioni and Poncelet, 1974;Onega and Kisner, 1978;Schulz and Lee, 1980;Kobayashi and Yoshikuni, 1982;Moon and Han, 1982;Teachman and Onega, 10.3389/fenrg.2023.1111357 1983; Gondal and Axford, 1986;Berkan et al, 1991;Alten and Danofsky, 1993;Shimazu, 1995;Tiwari et al, 1996;Song and Cho, 1997;Song et al, 1999;Domingos et al, 2003;Marseguerra et al, 2003;Obaidurrahman and Doshi, 2011;Chang, 2016;Pradhan et al, 2016;Zarei et al, 2016). Whereas principles regarding the neutron kinetics are the same for the load-following operations, the objective functions for the control methods differ-typically, axial offsets of the thermal power density, 135 Xe and 135 I concentrations are observed.…”

Section: Feedback From 135 Xe Build-upmentioning

confidence: 99%

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An overview of power reactor kinetics and control in load-following operation modes

et al. 2023

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Previous work done on reactor kinetics and control in load-following operation modes available in open literature is reviewed. The analysis is focused on, however not limited to pressurized water reactors. Different approximations of the time-dependent neutron transport problem as well as different control algorithms are described in detail and compared. Due to lack of published information the majority of the comparisons was done on qualitative level. In order to facilitate future testing and intercomparisons of models and algorithms, two so-called reference scenarios with time-dependent power demand are defined: a scenario to test the limitations of the load-following capabilities of the nuclear facilities and a second, quasi-realistic scenario.

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Section: Feedback From 135 Xe Build-upmentioning

confidence: 99%

“…The code TRIKIN (Obaidurrahman et al, 2010) is a 3D multigroup time-dependent diffusion code with a 1D lumped thermalhydraulic feedback module. With an added 135 Xe build-up module it was used by (Obaidurrahman and Doshi, 2011) to study the spatial stability of the system.…”

Section: Multi-energy-group Multi-region Kineticsmentioning

confidence: 99%

An overview of power reactor kinetics and control in load-following operation modes

et al. 2023

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“…1. The main reactor operating conditions and design parameters are presented in Table 1 [1]. The fuel assemblies of VVER-1000 and VVER-1200 are actually identical in design.…”

Section: Description Of the Reactormentioning

confidence: 99%

“…Light water reactors (LWRs) are the main suppliers of nuclear electricity. The VVER reactors belong to the family of the pressurized water reactors [1]. The VVER-1200/AES-2006 is the evolution of the VVER-1000 by improving plant performance and increasing plant safety.…”

Section: Introductionmentioning

confidence: 99%

Analyze the effect of void fraction on the main operating parameters of the VVER-1200

Galahom

2019

Arab Journal of Nuclear Sciences and Applications

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The VVER-1200/AES-2006 is one of the most promising nuclear reactors for power generation. This work provides an in-depth analysis of the void fraction effect on the operation of VVER-1200 using MCNPX code. The void fraction in the VVER-1200 may be a result from the loss of coolant accident (LOCA) or boiling the moderator/coolant materials. The fission multiplicities (υ), the estimated of the recoverable energy per fission (Q) and the effective delayed neutrons fraction (β eff ) have been investigated at different fuel enrichment and a different void fraction. It is beneficial to calculate the β eff at the different void fraction and different enrichment, due to its impact on the reactor power change rate. The excess reactivity in the reaction can be controlled using the gadolinium dioxide or boron carbide. Increasing the void fraction decrease the burnup rate of gadolinium dioxide and boron carbide in the VVER-1200 assembly. The Doppler coefficient has a large effect on the reactivity of the reaction. Therefore, it is important to calculate the Doppler coefficient at different fuel temperature. The existence of the void fraction increases the concentration of the most hazardous radioactive nuclear waste products.

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