Friday, July 31, 2009

Fundamental Handbook of Nuclear Physics and Reactor Theory

This is a useful handbook for understanding the basic of Nuclear Physics and also about reactor theory. The book is devided into two major modules. The first module is explaining the basic characterisics of atomic and nuclear physics which introduces concepts of atomic physics including the atomic nature of matter, the chart of the nuclides, radioactivity and radioactive decay, neutron interactions and fission, and the interaction of radiation with matter.
Next on the second module mainly as an advance theory than first. The second module provides information on reactor theory and neutron characteristics. Includes topics such as neutron sources, neutron flux, neutron cross sections, reaction rates, neutron moderation, and prompt and delayed neutrons


Overview
The Department of Energy Fundamentals Handbook entitled Nuclear Physics and Reactor Theory was prepared as an information resource for personnel who are responsible for the operation of the Department's nuclear facilities. Almost all processes that take place in a nuclear facility involves the transfer of some type of energy. A basic understanding of nuclear physics and reactor theory is necessary for DOE nuclear facility operators, maintenance personnel, and the technical staff to safely operate and maintain the facility and facility support systems. The information in this handbook is presented to provide a foundation for applying engineering concepts to the job. This knowledge will help personnel understand the impact that their actions may have on the safe and reliable operation of facility components and systems.



The Nuclear Physics and Reactor Theory handbook consists of four modules that are contained in two volumes. The following is a brief description of the information presented in each module of the handbook.

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Thursday, July 30, 2009

Robotic vocabulary building using extension inference and implicit contrast

TWIG (“Transportable Word Intension Generator”) is a system that allows a robot to learn compositional meanings for new words that are grounded in its sensory capabilities. The system is novel in its use of logical semantics to infer which entities in the environment are the referents (extensions) of unfamiliar words; its ability to learn the meanings of deictic (“I,” “this”) pronouns in a real sensory environment; its use of decision trees to implicitly contrast new word definitions with existing ones, thereby creating more complex definitions than if each word were treated as a separate learning problem; and its ability to use words learned in an unsupervised manner in complete grammatical sentences for production, comprehension, or referent inference. In an experiment with a physically embodied robot, TWIG learns grounded meanings for the words “I” and “you,” learns that “this” and “that” refer to objects of varying proximity, that “he” is someone talked about in the third person, and that “above” and “below” refer to height differences between objects.

Follow-up experiments demonstrate the system’s ability to learn different conjugations of “to be”; show that removing either the extension inference or implicit contrast components of the system results in worse definitions; and demonstrate how decision trees can be used to model shifts in meaning based on context in the case of color words.

Introduction
Robots that could understand arbitrary sentences in natural language would be incredibly useful—but real vocabularies are huge. American high school graduates have learned, on average, about 60,000 words [29]. Programming a robot to be able to understand each of these words in terms of its own sensors and experience would be a monumental undertaking. To recognize the words in the audio stream is one thing; to recognize their referents in the real world, quite another. The messy, noisy nature of sensory input can render this difficult problem intractable for the programmer. It would be far more useful to have a robot that is able to learn the meanings of new words, grounded in its own perceptual and conceptual capabilities, and ideally with a minimum of user intervention for training and feedback. The present paper describes a system that is built to do exactly that.

According to the developmental psychology literature, children can learn new words rapidly [7] and in a largely unsupervised manner [9]. From the time that word learning begins around the age of one, children’s word learning accelerates from a rate of about word every 3 days for the first 4 months [14], to 3.6 words a day between the ages of 2 12 and 6 [1,4,14], to 12 words a day between the ages of 8 and 10 [1]. This learning would impose quite a demand on the time of parents and educators if children had to be taught all these words explicitly, but instruction does not appear to be necessary for learning language [4,27], and in fact there are communities in which children learn to speak with hardly any adult instruction at all [21]. Thus, in designing a robotic system built to learn the meanings of words quickly and without supervision, it makes sense to study the heuristics that children appear to use in learning the meanings of words.

One strategy that children use is to infer what object or person an new word is referring to from its grammatical context—realizing that “sibbing” must refer to a verb, but “a sib” must refer to a noun [6]. Another strategy children use is to contrast the new word with other words they know in order to narrow down its meaning without explicit feedback [7,9,26]. For instance, a child may believe at first that “dog” refers to all four-legged animals, but on learning the word “cat,” the child realizes that implicitly, the meaning of “dog” does not include cats, and so the definition of “dog” is narrowed.


This paper describes a word learning system called TWIG that employs both of these strategies, using sentence context and implicit contrast to learn the meanings of words from sensory information in the absence of feedback. Until now, research into learning the semantics of words in an unsupervised fashion has fallen primarily into two camps. On the one hand, there have been attempts to learn word semantics in simulation, with the world represented as collections of atomic symbols [12] or statements in predicate logic [41]. These simulations generally assume that the robot already possesses concepts for each of the words to be learned, and thus word learning becomes a simple problem of matching words to concepts. Such systems can deal with arbitrarily abstract concepts, because they never have to identify them “in
the wild.”

On the other hand, systems that have dealt with real sensor data have generally assumed that concepts and even word boundaries in speech must be learned at the same time as words. Since learning abstract concepts directly from sensor
data is difficult, these systems have focused on learning words for physical objects [37] and sometimes physical actions [48].

The TWIG word-learning system is an attempt to bridge this divide. “TWIG” stands for “Transportable Word Intension Generator.” It is “transportable” in the sense that it does not rely too heavily on the particular sensory setup of our robot (Fig. 1), but could be moved with ease to any robot that can express its sensory input in Prolog-like predicates that can include numeric values. (Note that it is the learning system, and not the definitions learned, that is transportable; each robot using TWIG will learn definitions specific to its own sensory capabilities.) A “word intension” is a function that, when applied to an object or relation, returns true if the word applies. In other words, an intension is a word meaning [8,13]. Though TWIG was originally designed to solve the conundrums posed by pronouns, which themselves straddle the boundary between the abstract and the concrete, its techniques are more generally applicable to other word categories, including verbs, prepositions, and nouns.

The first technique that TWIG introduces is extension inference, in which TWIG infers from sentence context what actual object the new word refers to. For example, if the system hears “Foo got the ball,” and it sees Bob holding the ball, it will assume that “Foo” refers to Bob; the entity in the world that is Bob is the extension of “Foo” in this example. Doing this allows the system to be picky about what facts it associates with a word, greatly reducing the impact of irrelevant information on learning. Grammatical context also informs the system as to whether it should be looking for facts about a single object or a relation between objects, as with prepositions and transitive verbs.

Second, to build word definitions, the system creates definition trees (see Section 4.3). Definition trees can be thought of as reconstructing the speaker’s decision process in choosing a word. The interior nodes are simple binary predicates, and the words are stored at the leaves. The meaning of a word can be reconstructed by following a path from the word back to the root; its definition is the conjunction of the true or negated predicates on this path. Alternately, the system can choose a word for a particular object or relation by starting at the root and following the branches that the object satisfies until arriving at a word.

Definition trees are a type of decision tree, and are created in a manner closely following the ID3 algorithm [32]—but treating word learning as a problem of word decision, with words defined in terms of the choices that lead to them, is an approach novel to TWIG. Previous robotic systems have typically assumed that word concepts can overlap with each other arbitrarily [37,48]. In assuming that words do not overlap, TWIG actually allows greater generalization from few examples, because the boundaries of each concept can extend all the way up to the “borders” of the other words. Though we described an earlier version of the TWIG system in a previous conference paper [17], that version of TWIG did not make use of the definition tree method, which we developed later [15]. (Definition trees were originally simply called “word trees,” but this led to some confusion with parse trees.)

The latest version of TWIG includes several enhancements that were not present in any previously reported results, including part-of-speech inference, online vocabulary updates that allow new words to be used immediately, and better handling of negated predicates. This paper also presents a new quantitative evaluation of the two halves of the system, and some new experiments that demonstrate the system’s flexibility in building on its previous vocabulary and learning multiple definitions for the same word.


By : Kevin Gold, Marek Doniec, Christopher Crick, Brian Scassellati

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Wednesday, July 29, 2009

A 2D numerical simulation of sub-cooled flow boiling at low-pressure and low-flow rates

The main purpose of this study is to apply a two-fluid mathematical model to numerical simulation of two phase flow at low-pressure condition. Although models of sub-cooled boiling flow at one-dimension and high-pressure have been studied extensively, there are few equivalent studies for numerical simulation at two-dimension and low-pressure (1–2 bar) conditions. Recent literature studies on sub-cooled boiling flow at low-pressure have shown that empirical models developed for high-pressure situations are not valid at low-pressures. Since the mathematical model used in this study is accomplished at low-pressure, the transport equations for the variables of each phase are substituted in low-pressure. The governing equations of two-phase flow with an allowance to inter-phase transfer of mass, momentum and heat, are solved using a two-fluid; non-equilibrium model. The finite volume discretization scheme is used to create a linearized system of equations that are solved by SIMPLE staggered grid solution technique for a rectangular channel.

Improvement of the void fraction prediction of our model for the case of low-pressure sub-cooled flow boiling conditions was achieved. It is found that the heat transfer due to evaporation and surface quenching is higher than that by convection. Good agreement is achieved with the predicted results against the experimental data’s available in the literatures for a number of test cases.

Introduction
Boiling occurs when the temperature of the heater surface exceeds the saturation temperature, thus causing bubble formation. If the bulk temperature of the liquid is below saturation, the process is known as sub-cooled boiling. Sub-cooled flow boiling
is an important heat transfer regime in nuclear reactors. The proper prediction of the void fraction profile and other important parameters under sub-cooled flow boiling conditions is of primary importance in thermal-hydraulic safety analysis of nuclear reactors. In the nuclear area, ensuring the safe operation of a power or research reactor is of paramount importance especially where nuclear safety analyses concern the ability to predict the void fraction distributions and other two-phase flowparameters in sub-cooled boiling conditions. In the present state-of-the-art, the
two-fluid model can be considered as the most detailed and accurate macroscopic formulation of the thermal-hydraulic dynamics of two-phase flowsystems(Konˇcar andMavko, 2003). Within the flow field equations, expressed by conservation of mass,momentumand energy for each phase, interfacial transfer terms appear in each of
the equations to couple the different phasic effects. These terms determine the rate of phase changes and the degree of mechanical and thermal non-equilibrium between phases. Much success of the two-fluid model depends on these essential closure relations, which should be modelled accurately.



Most available sub-cooled boiling flow models are developed and tested at high-pressure (above 10 bar), and one-dimension conditions typical of power reactors, but there are few equivalent studies for numerical simulation at two-dimension and
low-pressure conditions. For a number of years, an internationally coordinated effort has been carried out, focusing on continuous development and validation of best-estimate thermalhydraulic computer codes, e.g. RELAP5, TRAC, CATHARE and ATHLET. These codes are used to perform predictive safety analyses of system transients, e.g. loss-of-coolant accidents (Petelin et al., 1994; Parzer et al., 1995; Wang and Mayinger, 1995; Tuunanen et al., 2000). According to the analyses of Woodruff et al. (1996), Hari et al. (1998), Hari and Hassan (2002), Tu and Yeoh
(2002,2006), Ustinenko et al. (2007), the codes, which have been developed and validated for high-pressure conditions, cannot be applied to low-pressure conditions without adequate modifications.

Extensive studies have addressed stability at low-pressure startup of natural circulation BWRs. Aritomi et al. (1992) and Chang et al. (1992,1993) conducted basic studies on instabilities under lowpressure condition in a parallel channel natural circulation loop using a two-fluid model. Tu and Yeoh (2002) improved the CFX1
code for the sub-cooled boiling flow at low-pressure condition and applied it to numerical simulation of vertical boiling channel. They found a reasonable agreement with the experimental results of Zeitoun and Shoukri (1997). Anglart (1993) studied the sub-cooled boiling at low-pressure condition in a vertical channel. He found
that the rate of vapor generated in low-pressure condition is higher than that in high-pressure condition. Recently, Mi et al. (1998) further developed the CFX sub-cooled boiling model and validated the model against Bartolomei et al.’s (1982) high-pressure boiling experiments.

The main objective of this study is to apply a two-fluid mathematical model to numerical simulation of two-phase flow in a vertical boiling channel at low-pressure condition, which is appropriate for research reactors. Our simulation is accomplished at low-pressure, therefore the interfacial area phenomena are substituted in low-pressure. Since the sensitivity of boiling to various parameters is much higher at low-pressure, in order to show all of the effects are properly captured, the predicted results are compared with the experimental data’s of Zeitoun and Shoukri (1997) for several test cases.

Conclusion
A two-dimensional; non-equilibrium two-fluid mathematical model was applied to predictions of low-pressure; low-flow subcooled boiling, using the phasic correlations being suitable for low-pressure condition. Improvement of the void fraction prediction of our model for the case of low-pressure sub-cooled flow
boiling conditionswas achieved. Applied numerical method in this work is in the good agreement with existing experimental data’s in low-pressure condition. It is found that the buoyancy force plays an important role on the void fraction evolvement. Density of bubbles is maximum near the walls and due to diffusion phenomena its effectiveness is developed to center of channel. With increasing in length of channel void fraction is increased, due to convection of bubble. Also because the effects of buoyancy and drag forces, the vapor velocity is increasing rapidly along the channel. It is found that the heat transfer due to evaporation and surface quenching is higher than that by convection.

Finally, it should be noted that, in high flow rates, some kind of additional phenomena such as bubbles coalescence and break-up appears, therefore in order to consider these effects, it is necessary to equip the formulation with a turbulence model.


By : Said Talebi, Farshad Abbasib, Hadi Davilu

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Tuesday, July 28, 2009

Static analytical and experimental research of shock absorber to safeguard the nuclear fuel assemblies

The Ignalina Nuclear Power Plant (NPP) has two RBMK-1500 graphite-moderated boiling water multichannel reactors. The Ignalina NPP Unit 1 was shutdown at the end of 2004, while Unit 2 is foreseen to be shutdownat the end of 2009.At the Ignalina NPPUnit 1 remains approximately 1000 spent fuel assemblies with lowburn-up depth. A special set of equipmentwas developed to reuse these assemblies in the reactor of Unit 2. One of most important items of this set is a container, which is used for the transportation of spent fuel assemblies between the reactors of Unit 1 and Unit 2. A special shock absorber was designed to avoid failure of fuel assemblies in case of hypothetical spent fuel assemblies drop accident during uploading/unloading of spent fuel assemblies to/from container. This shock absorber was examined by using scaled experiments.

The objective of this article is the estimation whether the proposed design of shock absorber fulfils the function of the absorber and the optimization of its geometrical parameters using the results of the performed investigations.Static analytical and experimental investigations are presented in the article. The finite element code BRIGADE/Plus was used for the analytical analysis. The calculation model was verified by comparing the experimental investigation and simulation results for further employment of this finite element model in the development of an optimum design of shock absorber. Static simulation was used to perform primary optimization of design and dimension of the shock absorber.

Introduction
Ignalina Nuclear Power Plant (NPP) comprises two units with RBMK-1500 water-cooled graphite-moderated channel-type power reactors (Almenas et al., 1998). One of the specific features of RBMK type reactor is that refuelling is performed during power operation, the average burn-up depth of fuel is kept constant during all operational life of the reactor. After the reactor shutdown for decommissioning there is a substantial amount of fuel assemblies in the reactor with low burn-up depth considerably lower than design burn-up depth). Such fuel assemblies have high energetic potential and can be reused. After the shutdown of Ignalina NPP Unit 1 in 2004, approximately 1000 fuel assemblies from Unit 1 are applicable for further reuse in the reactor of Unit 2. The projectwas initiated to use fuel of Unit 1 in Unit 2, and special equipment was designed for this purpose. The schematic sketch of the equipment for loading/unloading of the fuel assemblies is presented in Fig. 1.

Transportation of spent fuel assemblies (SFA) fromUnit 1 to Unit 2 is carried out in the container designed for the maintenance of radiation and nuclear safety during transportation of SFA between power plant units. The container (see Fig. 1) is placed on the transport vehicle and represents the steel thick-walled cylindrical vessel, providing the arrangement of basket with six SFA, protection from ionizing radiation, retention of radionuclides within the container and SFA integrity during transportation.

The transport container is one of the most important components of the spent fuel transportation equipment set. Spent nuclear fuel multi-canister overpack (MCO) drop analysis (Rains, 1999) has revealed that overpack drop into the cask can produce very large impact reactions on the MCO and internals. Therefore spent fuel storage and transport cask must withstand various accident conditions such as free drop and puncture (Lee et al., 2004) in accordance with the requirement of the IAEA and national regulations. To assess potential damage to the various components that comprise the cask deformation tests of the structural material were performed along with the theoretical simulations for the shock absorber design (Sappok et al., 1994 and Pfeiffer and Kennedy, 1989). Despite the fact that container is used for on-site transportation of RBMK fuel,the requirements for its design in some aspects are even stronger than in the case of off-site transportation, because the fuel after the transportation shall be applicable for the reuse in the reactor of Unit 2. The equipment shall assure the required safety level even in case of most dangerous hypothetical accident.During loading/unloading of the basket with six SFA into a container, theoretically, the accident with drop of a basket from height of 17.5mto a container chamber is possible. The basket is supplied with brake arrangement, which in case of accidental drop ensures slowdown of a basket due to frictional force at the shaft walls. The full stop of the basket inside the container is ensured by the shock absorber (see Fig. 1).
Main requirements to the construction of the shock absorber:
- Keepweight of the loaded basket inside the container at a vertical position (normal operating conditions) without plastic deformation of the shock absorber.
- During the loading of fuel assemblies absorber must ensure damping due to elastic deformation.
- Absorb all kinetic energy of the dropping basket in case of the accident.
- Provide smooth slowdownof the loaded basket up to the full stopping on a condition that acceleration force (load) affecting the fuel loaded basket will not cause the breakdown of a SFA.
- Design of the shock absorber must prevent buckling of shock absorber and reduction of the inner diameter.
- Easy decontamination of radionuclides from the surface of shock absorber during the service.

In thiswork the static characteristics of the shock absorber models under the axial compression were determined. The comparison of the experimental and simulated results was carried out and the optimization of the construction of the shock absorber was performed.

Conclusion
Shock absorber design for use in transport container for spent nuclear fuel assemblies was proposed which represents a steel hollow cylinder with the cuts. Static analytical and experimental investigations of the shock absorber models were carried out in order to optimize geometrical parameters and damping characteristics
of the full-scale absorber. The finite element method was used for the analytical investigation of the shock absorber using the state-of-the-art BRIGADE/Plus code. Tests revealed that axial compression of the models of the given construction occurs with the retention of a uniform and smooth increase in the magnitude of force and displacement. Obtained, almost horizontal characteristic of breaking force shows that constant braking force will be maintained.

It was found that the decrease of diameter of the models during compression is relatively small. Testing of the model and simulation results shows that its symmetrical construction retains stability during compression. During the loading of fuel assemblies damping due to elastic deformation also will be ensured. The deformation curves of the shock absorber were defined by both investigations. Good agreement of simulation and experimental datawas received. With respect to the separately tested samples, the deviation of calculation data fromthose established experimentally does not exceed 5% for both model I and II. The obtained results enable to make a statement that the static FE method can be used for optimization of construction of the given design of shock absorber.


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By :Gintautas Dundulisa, Albertas Grybenasb, Renatas Karalevicius, Vidas Makarevicius, Sigitas Rimkevicius, Eugenijus Uspurasa

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