Showing papers in "Annals of Nuclear Energy in 2005"

TL;DR: A neural adaptive inverse controller is used to control the power of a PWR reactor and the stability of the system and convergence of the controller parameters are guaranteed during online adaptation phase provided the controller is near the plant’s real inverse after offline training period.

TL;DR: In this article, a system of Ito stochastic differential equations is derived that model the dynamics of the neutron density and the delayed neutron precursors in a point nuclear reactor.

TL;DR: The FAST project at PSI as discussed by the authors developed a unique analytical code capability for the core and safety analysis of advanced critical (and sub-critical) fast-spectrum systems for a wide range of different coolants.

TL;DR: This paper looks into the issue of using cluster analysis for transient classification in nuclear components and systems by taking an approach based on a different Mahalanobis metric for each cluster.

TL;DR: Two new wavelet bases are developed for discretising the angular term of the first-order Boltzmann transport equation and the wavelets proposed are based on Sweldens second generation wavelets, based on which the angular flux approximation takes the form of finite element linear and quadratic representations.

TL;DR: In this article, a new cooling scheme was devised to increase the average coolant core outlet temperature of the high temperature supercritical pressure light water Reactor (SCLWR-H).

TL;DR: An advanced fault detection and isolation technique was developed for the steam generator system of a typical pressurized water reactor (PWR) plant and the implementation of the FDI algorithm for both instrument and actuator monitoring is demonstrated.

TL;DR: In this paper, the development and verification of 1D version DYN1D-MSR of the code is described and validated with the experimental data gained from the molten salt reactor experiment performed in the Oak Ridge National Laboratory research is described.

TL;DR: In this article, the authors performed a safety analysis of the IAEA 10 MW MTR Pool type Research Reactor under flow blockage of a single Fuel Assembly (FA) conditions.

TL;DR: In this article, an atmospheric dispersion modeling and radiation dose calculations have been performed for a postulated accidental airborne radionuclide release from the Pakistan Research Reactor-1 (PARR-1) appropriate to a power upgrade to 10MW.

TL;DR: In this article, the authors studied the possibility of creating a self-organizing non-linear regime in the form of a running wave of nuclear burning in a critical fast neutron reactor.

TL;DR: In this article, the authors consider the flow in a fuel rod bundle as a case study and discuss why the application of the standard k- e model fails to give reasonable results in this situation.

TL;DR: In this paper, a three-dimensional one-group diffusion model with explicit effects of burnup and feedback is studied for a so-called "candle reactor" with a solitary wave profile in the long axial direction and a buckling shape, as in usual reactors, in the smaller transverse direction.

TL;DR: Robust AutoAssociative Neural Networks (RAANN) are applied to a series of signals produced by the Halden simulator of the 1200 MWe BWR Forsmark-3 plant in Sweden, allowing a deep understanding of the network functioning and also avoiding the traditional and troubling procedure of selection by trial-and-error.

TL;DR: In this paper, an effective method of calculating the pulsed Feynman-alpha formula for finite width pulses is introduced and applied and is suitable for calculating both the deterministic and the stochastic FCA formulae, while also being capable of treating various pulse shapes through very similar steps and partly identical formsulae.

TL;DR: Algebraic preconditioners, renumbering techniques and a two-level algebraic multigrid method have been implemented to speed up the Krylov iterations of the DPN equations used for the acceleration of the method of characteristics in unstructured meshes.

TL;DR: In this paper, an approximation of few-group neutron cross-sections by functions of burnup and thermal-hydraulics parameters of a fuel cell is considered, where the cross-section is written as a sum of two terms: the base cross-sectional area, which depends only on burnup, and the deviation, which is computed under the nominal reactor core conditions.

TL;DR: Rothenstein et al. as mentioned in this paper used S(α,β) tables for evaluating the secondary energy distribution for heavy isotopes with pronounced resolved resonances in the vicinity of resonances.

TL;DR: In this article, the authors have developed an effective solution technique for calculating the pulsed Feynman- and Rossi-alpha formulae, which can easily handle various pulse shapes of a pulsed neutron source.

TL;DR: In this paper, a new fission penetrability model taking into account a triple humped barrier has been developed, and a clear improvement has been observed for K effective validation tests (up to 30 MeV) with this new evaluation.

TL;DR: In this article, the authors developed a nonlinear numerical model for a double-channel two-phase natural circulation loop and analyzed the dynamics and stability boundary of the double channel boiling NCL.

TL;DR: In this article, a continuous energy Monte Carlo code is used for the assembly calculations of actual BWR core analysis, and the calculated core parameters showed good agreement with the results of the on-line core monitoring system of HAMAOKA-3.

TL;DR: In this paper, an attempt to improve the evaluation of the prompt fission neutron spectrum of 252 Cf(SF) is made, where the multi-modal fission concept is included into the Los Alamos model.

TL;DR: In this paper, the authors investigated the possibility of localising a noise source of the type D absorber of variable strength D (or reactor oscillator) from as few as five neutron detectors evenly distributed throughout the core of a commercial nuclear reactor.

TL;DR: In this paper, experimental estimates of a subcritical level using rod-drop and pulsed neutron source (PNS) techniques are presented, and it is shown that the area PNS method is the least space-dependent and the most accurate.

TL;DR: The results of the research and the experiments show that the diagnosis algorithm is proven to be a good solution for identifying the failures of the check valves without any disassembling work.

TL;DR: In this article, a dynamic control rod reactivity measurement (DCRM) technique has been developed and applied to six startups of Westinghouse plants as well as Korea Standard Nuclear power Plants based on the Combustion Engineering System 80 NSSS.

TL;DR: A feature selection algorithm is proposed based on the extension to the transient case of a classifiability index which can be directly computed from the plant measured data and used to filter out irrelevant or redundant features.

TL;DR: In this article, a two-phase flow instability in natural circulation loops of China Advanced Research Reactor (CARR) has been investigated, and the calculated results have important significance for the safety operation and accidental analysis of CARR.

TL;DR: Theoretical calculation of thermal hydraulic characteristics of CARR shows that the activity of emergency cooling system apparently reduces the peak temperatures of fuel and coolant, peak quality and other operation parameters, thus it effectively ensures the safety in operation ofCARR.