Showing papers in "Progress in Nuclear Energy in 2007"

TL;DR: In this article, the authors deal with actinide-bearing materials that support the latter approach and develop matrices for the immobilization of plutonium and minor actinides, Np, Am and Cm.

TL;DR: In this paper, the state-of-the-art of flow instabilities in natural circulation boiling loops has been reviewed by reviewing a number of contributions made in the past three decades.

TL;DR: In this paper, a measuring system with a collimator was designed and fabricated and a concrete sample with collinear cracking was designed to quantify the effect of cracks on shielding performance in a concrete body.

TL;DR: The proposed system using a two level classifier architecture with a DNNA model instead of the conventional single general purpose neural network for fault diagnosis can provide more accurate numerical values other than qualitative approximation for transient's severity.

TL;DR: In this article, a loss of coolant accident (LOCA) in Tehran research reactor (TRR) is analyzed and two main loss of coolingant accidents are simulated and developed to analyze LOCA in TRR.

TL;DR: In this paper, the authors developed a mathematical model to predict the behavior of the pump during start-up transient condition, based on a working practical approximation in that the total startup time is reduced by one third.

TL;DR: For example, underground isolation of dangerous, including radioactive, wastes is increasingly being used as a safe and reliable method of final disposal as discussed by the authors, which offers sound evidence that deep geologic isolation is effective, safe, and compatible with responsible environmental stewardship.

TL;DR: In this paper, the main technique suggested for transmutation of nuclear waste is described, which significantly reduces the time during which repositories have to be sealed, simplifying the task of protecting future generations from the radioactive remnants of our civilisation.

TL;DR: This issue is addressed by the development of subjective probability distributions relative to the physical modes of failure for a typical passive system for reactor decay heat removal, operating in natural circulation.

TL;DR: It may be difficult or impossible to incorporate passive systems extensively in large size reactors, but could be well fit into small and medium sized reactors.

TL;DR: In this paper, the reaction coefficients analysis of the Bushehr nuclear power plant (BNPP), VVER-1000, at nominal conditions is carried out during its first operational cycle where they used WIMS and CITATION codes in their theoretical studies.

TL;DR: A derivation of a wide range of objectives, evaluation viewpoints from research professionals and evaluators, and evaluation criteria is presented, to structure and quantify the criteria and research performance of some selected projects.

TL;DR: In this article, a structural approach based on the results of EXAFS and NMR spectroscopy suggests that the structural role of the trivalent and tetravalent elements corresponds to that of intermediate network modifiers and intermediate network formers, respectively.

TL;DR: After recalling the space-time kinetics equations, the finite-element method is presented as a general discretization technique and then applied to the so-called nodal diffusion methods, both primal and mixed-hybrid ones, for the space discretizations.

TL;DR: In this paper, the results of the point-reactor neutron kinetics equations for different analytic models are investigated and compared with those given in the published literatures, and the validity and valid limit of these analytic models and related solutions are determined and discussed.

TL;DR: In this paper, an interactive combination of Phoswich detector array (PDA) and differential absorption lidar (DIAL) is proposed to trace the unknown radioactive plumes released into the atmosphere from a reactor stack, containment of the nuclear power plants, radioisotope separation laboratories, reprocessing plants or the uranium conversion facilities.

TL;DR: A demonstration of the maturity level achieved in the calculation of 3-D core performance during complex accident scenarios in NPPs is emphasized and typical applications are outlined and discussed showing the main features and limitations of this technique.

TL;DR: In this paper, the status of the fuel research and some recent developments are given, as well as the option to utilize this plutonium in advanced fuel types, such as thorium-based and inert matrix fuels.

TL;DR: The aim of this paper is to give a complete overview of the kp method applications and limits and compared to reference measurements as well as to PNS measurement analysis like exponential fitting or area methods.

TL;DR: In this article, a simulation model is developed to simulate the coupled kinetics and thermal-hydraulics of material testing Reactors (MTR) with simple means, which is used to analyze the series of benchmark transients specified for IAEA 10MW research reactor.

TL;DR: In this paper, a SWOT analysis is employed to identify the internal strengths and weaknesses of nuclear energy when compared with other energy competitors on the basis of an evaluation of the external factors which are likely to play the roles of opportunities (O) for and/or threats (T) against the technological changes in nuclear energy.

TL;DR: In this article, a sub-channel thermal-hydraulic analysis code named SUBCHAN was developed to analyze super critical CANDU type reactor which has such characters as horizontal fuel channels, heavy water moderated, super critical light water cooled, any type of fuel bundle with or without thorium rods.

TL;DR: In this paper, the authors presented the results of thermal-hydraulic calculation of the blackout analysis for VVER-1000/V320 units at Kozloduy nuclear power plant (KNPP), done during the development of symptom based emergency operating procedures (SB EOPs) for this plant.

TL;DR: An overview of current nuclear power generation and fuel cycle strategies in Europe is presented in this article, with an emphasis on options for the management of separated plutonium in the medium to long term.

TL;DR: In this article, the effect of bentonite and ash additives on the leaching and strength properties of a cement-resin matrix was investigated and the optimum ratio of resin to matrix material was between 0.36 and 0.67.

TL;DR: In this paper, a lead-alloy cooled fast reactor, PEACER (Proliferationresistant, Environment-friendly, Accident-tolerant, Continuable energy, and Economical Reactor), has been designed by a university research team in Korea.

TL;DR: The primary question addressed in this work is for a given problem size, which domain decomposition scheme, angular or spatial, is best suited to parallelize discrete ordinates methods on a specific computational platform?

TL;DR: In this article, a nodal-scheme has been developed for modeling the behavior of fission products in the primary circuit of a typical PWR under flow rate transients.

TL;DR: In this paper, the authors proposed a reliable and effective management of this radioactive waste and spent nuclear fuel in association with the introduction of next generation GEN-IV reactors has become an important challenge to nuclear energy.

TL;DR: The potential role of Generation IV nuclear energy systems in managing plutonium was discussed in this paper, where the potential for the management of plutonium using Generation IV systems was briefly reviewed from a complete fuel cycle perspective to illustrate the issues in the context of a fleet of reactor and fuel cycle facilities.