bluuebunny/crossref_metadata_2025 huggingface dataset:
Is no praise good praise? Effects of positive feedback on children's and university students’ responses to subsequent failures
Authors: Skipper Yvonne , Douglas Karen
Published: April 2011

Background. According to Dweck and colleagues, praise can be delivered using person (‘you are clever') or process terms (‘you worked hard'). Research suggests that giving people process praise after success can help them deal better with subsequent failures because it attributes outcomes to effort rather than fixed ability. However, research has thus far inadequately addressed how these types of praise compare to receiving no evaluative feedback.

Aim. The aim of the present research was to examine the effects of person and process praise compared to a control group where only objective outcome feedback was given.

Samples. In Study 1, 145 British school children aged 9–11 years took part. In Study 2, participants were 114 British university students.

Method. In both studies, participants read three scenarios and were asked to imagine themselves as the main character. In each scenario, they succeeded in an educational task and received either person, process, or no praise. Participants then read two scenarios, where they failed at a task. Following each scenario participants evaluated their performance, affect, and persistence.

Results. After one failure, participants who received person praise reacted most negatively on all dependent measures. However, those in the process condition did not differ significantly from those in the control group.

Conclusions. These findings suggest that process feedback may not be inherently positive; instead person feedback seems particularly detrimental.
Speechreading and the Bruce–Young model of face recognition: Early findings and recent developments
Authors: Campbell Ruth
Published: April 2011

In the context of face processing, the skill of processing speech from faces (speechreading) occupies a unique cognitive and neuropsychological niche. Neuropsychological dissociations in two cases (Campbell et al., 1986) suggested a very clear pattern: speechreading, but not face recognition, can be impaired by left‐hemisphere damage, while face‐recognition impairment consequent to right‐hemisphere damage leaves speechreading unaffected. However, this story soon proved too simple, while neuroimaging techniques started to reveal further more detailed patterns. These patterns, moreover, were readily accommodated within the Bruce and Young (1986) model. Speechreading requires structural encoding of faces as faces, but further analysis of visible speech is supported by a network comprising several lateral temporal regions and inferior frontal regions. Posterior superior temporal regions play a significant role in speechreading natural speech, including audiovisual binding in hearing people. In deaf people, similar regions and circuits are implicated. While these detailed developments were not predicted by Bruce and Young, nevertheless, their model has stood the test of time, affording a structural framework for exploring speechreading in terms of face processing.
Experimental Investigations of the Efficiency of Round-Sectioned Helical Strakes in Suppressing Vortex Induced Vibrations
Authors: Lubbad Raed K. , Løset Sveinung , Moe Geir
Published: April 2011

Vortex induced vibrations (VIVs) may cause a large amount of damage to deep water risers. Helical strakes are used as a mitigating measure to suppress these vibrations. The purpose of this paper is to verify the efficiency of round-sectioned helical strakes in suppressing VIV. It is believed that round-sectioned helical strakes can be more readily mounted on risers for intervention and maintenance compared with sharp-edged strakes that may have to be welded onto the risers. Systematic experimental investigations including 28 configurations of round-sectioned helical strakes were tested in an attempt to find the most suitable strake configuration. The experiments were performed in a steady flow flume with an elastically mounted rigid circular cylinder of 500 mm in length and 50 mm in outer diameter. The test cylinder was spring-supported in both the inline and cross-flow directions. The measurements were limited to mapping the displacement of the cylinder. First, the cylinder was tested without strakes as a reference case. The best configuration among the tested round-sectioned helical strake configurations was found to reduce the amplitude of oscillation relative to the bare cylinder case by 96% in the cross-flow direction and by 97% in the inline direction. The main features of this configuration are the number of starts (3), the pitch (5D), and the diameter of the strake (0.15D), where D is the outer diameter of the test cylinder. Additionally, this paper investigates the effects of varying pitch, the effects of surface roughness, and the effects of the ratio between the cross-flow and inline natural frequencies of the test rig on the efficiency of the suggested configuration of round-sectioned helical strakes.
Investigation of Stress Assisted Grain Boundary Oxidation Cracking in MAR-M002 High Pressure Turbine Blades
Authors: Selvig Austin , Huang Xiao , Hildebrand Mike , Stek David
Published: April 2011

Modern superalloys have enabled high pressure turbine (HPT) blades in gas turbine engines (GTE) to operate at higher temperatures. Unfortunately, the complexity of these materials can make it difficult to understand the failure mechanisms of these blades. HPT blades made of the nickel-based superalloy Mar-M002 have been found to suffer from stress assisted grain boundary oxidation (SAGBO) cracking. HPT blades removed from an RB211-24C aeroderivative industrial GTE were sectioned, and the cracks and microstructure were studied using scanning electron microscopy (SEM) and energy dispersive X-ray spectroscopy (EDS). No cracks were found on the external surface of the blade, which had been coated with an oxidation resistant material. Surface irregularities were found along the walls of the inner cooling channels throughout the entire blade. Larger SAGBO cracks were observed to be near the lower 25% span of the blade and had initiated from the surfaces of the cooling channels. SEM/EDS analyses showed that these cracks had large amounts of alumina and hafnium-rich particles within them. It is evident that these cracks occurred in locations where the combination of high stress and high temperature led to higher rates of oxygen diffusion and subsequent oxidation of grain boundary carbides. Hafnium carbide precipitates along the grain boundaries expanded as they converted into hafnium oxide, thus further increasing the stress. It is envisaged that this increase in stress along the grain boundary has caused the cracks to initiate and coalesce. Based on this observation, it is believed that the inner cooling channels of these HPT blades could benefit from the application of an oxidation resistant coating in order to prevent or delay the formation of these cracks.
On the Behavior of Water Droplets When Moving Onto Blade Surface in a Wet Compression Transonic Compressor
Authors: Sun Lanxin , Zheng Qun , Luo Mingcong , Li Yijin , Bhargava Rakesh
Published: April 2011

The process of wet compression in an axial compressor is an intricate two-phase flow involving not only heat and mass transfer processes but also droplet breakup and even formation of discontinuous water film on the blade surface and then breaking into droplets. In this paper, the droplet-wall interactions are analyzed using the theory of spray wall impingement through two computational models for an isolated transonic compressor rotor (NASA rotor 37). Model 1, representing spread phenomenon, assumes that all droplets impacting on the blade are trapped in the water film and subsequently released from its trailing edge and enter the wake region with an equivalent mass flow but bigger in diameter and smaller in number. Whereas, the model 2, representing splashing phenomenon, assumes that upon impacting on the blade, the droplets will breakup into many smaller ones. The three-dimensional flow simulation results of these two models are analyzed and compared in this paper.
Interaction of Waves With a Steady Intake/Discharge Flow Emanating From a 3D Body
Authors: Padmanabhan Bala , Ertekin R. Cengiz
Published: April 2011

It has been proposed that the warm surface-water intake pipes distributed around an OTEC plant can generate adequate momentum to globally position a platform to overcome the second-order drift forces, thereby eliminating the need for additional power for thrusters or for mooring lines. It is evident that if the intake rate of the flow is high, there will be interaction among the locally created steady flow due to the intake, the incoming wave, and the ensuing platform motions. In this work, we address such concerns by developing a linear theory for obtaining the motions (in the presence of incoming waves) of arbitrary 3D bodies from which there is a steady intake/discharge. The boundary-value problem is formulated within the assumption of the linear potential theory by decomposing the total potential into oscillatory and steady components. The steady potential is further decomposed into double-model and perturbation potentials. The time harmonic potential is coupled with the steady potential through the free-surface condition. The potentials are obtained using the quadratic boundary-element method. The effect of the steady flow on hydrodynamic force coefficients and response amplitude operators is studied.
Self-Powered Telemetric Torque Meter
Authors: Filho Abel Cavalcante Lima , Belo Francisco Antônio , Alves dos Santos Jerry Lee , Gomes dos Anjos Eudisley
Published: April 2011

This paper presents a self-powered telemetric torque meter. The idealized instrument uses strain gauge, telemetry, and LABVIEW graphic programming. The electronic transduction signal is transmitted by digital modulation from a remote transduction unit fixed to a rotation shaft to a base station sending signals to a personal computer (PC) by means of a virtual instrument developed in LABVIEW. The signal can also be delivered to other units besides the PC. The ZigBee/IEEE 802.15.4 protocol is the standard protocol for wireless communications and is highly used in industrial monitoring and control applications. A low-noise method for supplying the remote transduction unit components in the rotation shaft—using its rotating movement to generate the demanded energy—has also been developed. After extensive experimentation, the theoretical model seems to confirm the idea proposed. The system presented in this study is robust, precise, cost-effective, and has high-noise immunity even in abrasive and strong vibration environments.
NO and NO2 Concentration Modeling and Observer-Based Estimation Across a Diesel Engine Aftertreatment System
Authors: Hsieh Ming-Feng , Wang Junmin
Published: April 2011

This paper presents an experimentally validated control-oriented model and an observer for diesel oxidation catalyst (DOC)-diesel particulate filter (DPF) system in the context of exhaust gas NO and NO2 concentration estimations. NO and NO2 have different reaction characteristics within DPF and selective catalytic reduction (SCR) systems, two most promising diesel engine aftertreatment systems. Although the majority of diesel engine-out NOx emissions is NO, the commonly used DOC located upstream of a DPF and a SCR can convert a considerable amount of NO to NO2. Knowledge of the NO/NO2 ratio in exhaust gas is thus meaningful for the control and diagnosis of DPF and SCR systems. Existing onboard NOx sensors cannot differentiate NO and NO2, and such a sensory deficiency makes separate considerations of NO and NO2 in SCR control design challenging. To tackle this problem, a control-oriented dynamic model, which can capture the main NO and NO2 dynamics from engine-out, through DOC, and to DPF, was developed. Due to the computational limitation concerns, DOC and DPF are assumed to be standard continuously stirred tank reactors in order to obtain a 0D ordinary differential equation model. Based on the model, an observer, with the measurement from a commercially available NOx sensor, was designed to estimate the NO and NO2 concentrations in the exhaust gas along the aftertreatment systems. The stability of the observer was shown through a Lyapunov analysis assisted by insight into the system characteristics. The control-oriented model and the observer were validated with engine experimental data and the measured NO/NO2 concentrations by a Horiba gas analyzer. Experimental results show that the model can accurately predict the main engine-out/DOC/DPF NO/NO2 dynamics very well in semisteady-state tests. For the proposed observer, the predictions converge to the model values and estimate the NO and NO2 concentrations in the aftertreatment system well.
Environmental Remediation Activities at the Ningyo-Toge Uranium Mine, Japan
Authors: Saito Hiroshi , Taki Tomihiro
Published: April 2011

Ningyo-toge Uranium Mine is subject to the environmental remediation. The main purposes are to take measures to ensure the radiation protection from the exposure pathways to humans in future, and to prevent the occurrence of mining pollution. The Mill Tailings Pond in the Ningyo-toge Uranium Mine has deposited mining waste and impounded water as a buffer reservoir before it is transferred to the Water Treatment Facility. It is located at the upstream of the water-source river, and therefore, for the environmental remediation, the highest priority has been put to it among many facilities in the Mine. So far, basic concept has been examined and planning has been carried out for the remediation. Also, a great number of data has been acquired, and using the data, some remediation activities have already begun, including designing for the upstream part of the Mill Tailings Pond. According to the current plan, the Mill Tailings Pond will be covered by capping following dewatering and compressing of mill tailings. The capping is composed of “radon barrier” for lowering radon-gas dissipation and dose rate, and its protection layer. Natural materials are planned to be used for the capping to alleviate the future maintenance. After capping, data will be accumulated to verify the effectiveness of the capping, and if proved effective, it will be utilized for the capping of the downstream part.
Decommissioning Planning for Swedish Operating NPPs
Authors: Hedin Gunnar , Edelborg Mathias , Bergh Niklas , Carlsson Jan , de la Gardie Fredrik
Published: April 2011

Decommissioning studies have been carried out for the three BWR units of Oskarshamn nuclear power plant and the three BWR units of Forsmark nuclear power plant. The final closure of these units is far ahead but anyhow there has been a need for developing a more general decommissioning planning basis. The main objectives of the studies have been to establish an estimate of the waste amounts arising from these units during decommissioning and dismantling as well as providing a firm basis for funding of the decommissioning phase for these units. The waste amounts will be used when designing a repository for decommissioning waste of the same type as the existing facility for final disposal of short-lived low and intermediate level waste, the SFR, at Forsmark, Sweden. The broader studies will also be used to verify that the existing national decommissioning fund is of an adequate size. In this paper information is given about the inventory of materials and radioactivity at the time for final shutdown. Furthermore, the resulting waste quantities are estimated. Some other features of the decommissioning planning are also presented.
Radioactive Waste Management in Lebanon
Authors: Assi Muzna
Published: April 2011

The disused sealed radioactive sources including orphan sources in Lebanon, along with the growing industry of sealed radioactive sources in medical, industrial and research fields have posed a serious problem for authorities as well as users due to the lack of a national store for disused radioactive sources. Assistance from the International Atomic Energy Agency (IAEA) was requested to condition and store disused radium needles and tubes present at two facilities. The mission took place on July 25, 2001 and was organized by the IAEA in cooperation with the Lebanese Atomic Energy Commission (LAEC). Other disused radioactive sources were kept in the facilities till a safer and securer solution is provided; however orphan sources, found mainly during export control, were brought and stored temporarily in LAEC. The necessity of a safe and secure store became a must. Prior to October 2005, there was no clear legal basis for establishing such store for disused radioactive sources, until the ministerial decree no 15512 dated October 19, 2005 (related to the implementation of decree-law no 105/83) was issued which clearly stated that “The LAEC shall, in cooperation with the Ministry of Public Health, establish a practical mechanism for safe disposal of radioactive waste”. Following this, the work on inventory of disused sealed sources along with collecting orphan sources and placing them temporarily in LAEC was legally supported. Moreover, several missions were planned to repatriate category I and II sources, one of which was completed specifically in August 2009; other missions are being worked on. In 2008, a national technical cooperation project with the IAEA was launched. Under the Technical Cooperation (TC) project with reference number LEB3002, the project was entitled “Assistance in the establishment of a safe temporary national storage at the LAECfor orphan sources and radioactive waste” which cycle is 2009–2011. Under this project, a national store for radioactive sources in the third basement of LAEC is being established. The area is being reconstructed currently and will be equipped when ready under LEB3002 project. Along with this, a system for sealed disused sources management has been prepared, part of which is applied now and the rest will be applied upon the establishment of the store. This paper will cover the inventory collection process, the study for the establishment of this store, the present and prospective waste management system, and the waste acceptance criteria.
Radon Impact at a Remediated Uranium Mine Site in Japan
Authors: Ishimori Yuu
Published: April 2011

This paper mainly illustrates the radon impact of the closed uranium mine site remediated in 2007. The site remediated is the waste rock site located on the steep slope of a hill about 1.5 km upstream from a residential area along a main ravine. Major remedial action was to cover these waste rock yards with weathering granite soil. The radon flux density after remediation was intended to be 0.1 Bqm−2s−1 in consideration with the natural background level around Ningyo-toge because there is no value of radon flux density regulated in Japan. Our action decreased the radon concentration in the site to natural background level, approximately from 10 to 40 Bqm−3, although relatively high concentration in excess of 100 Bqm−3 was observed before remediation. On the other hand, our action did not decrease the radon concentrations around the site in general. This fact proved that the limited source such as waste rocks affected the radon concentrations at neighboring area only. The similar tendencies were also observed in other environmental data such as radon progeny concentrations. In conclusion, these findings proved that our remedial action was successful against radon. This fact will lead to more reasonable action plans for other closed mine sites.
Comparison of Post-Irradiation Experimental Data and Theoretical Calculations for Inventory Estimation of Long-Lived Fission Products in Spent Nuclear Fuel
Authors: Asai Shiho , Hanzawa Yukiko , Okumura Keisuke , Suzuki Hideya , Toshimitsu Masaaki , Shinohara Nobuo , Kaneko Satoru , Suzuki Kensuke
Published: April 2011

The inventory estimation of long-lived fission products (LLFP) is essential for the long-term safety assessment of a geological disposal of high-level radioactive waste (HLW). 79Se and 135Cs are a main contributor to the total dose from the geological repository of HLW, owing to their solubility in the strata. In this study, the post-irradiation experimental data of LLFPs, such as 79Se, 99Tc, 126Sn and 135Cs, were compared with ORIGEN2 calculation using the data library of JENDL-3.3. A fragment of the UO2 fuel pellet irradiated in a commercial Japanese PWR was dissolved with nitric acid in a hot cell. The resultant solution was filtered to remove insoluble residue. After Se, Tc, Sn, and Cs were chemically separated, the concentrations of 79Se, 99Tc, 126Sn and 135Cs were determined with an inductively coupled plasma quadrupole mass spectrometer (ICP-QMS). The concentration of 79Se, 99Tc, 126Sn and 135Cs in the sample solution were 0.78 ± 0.22, 101 ± 24, 3.2 ± 0.6, and 68 ± 6.0 ng/g of the sample solution (ng/g-sol.), respectively. The results for 79Se and 135Cs obtained in this study showed good agreement with those obtained through ORIGEN2 calculation. This indicates that ORIGEN2 calculation is applicable to the estimation of the amounts of 79Se and 135Cs generated during irradiation. In contrast, the experimentally determined concentration of 99Tc and 126Sn were equivalent to approximately 70% and 60%, respectively, of those obtained through ORIGEN2 calculation.
Detailed Standardized Decommissioning Parameters Calculation for Larger Technological Aggregates and Relevant Buildings in Nuclear Power Plants Using the OMEGA Code
Authors: Beza´k Peter , Danisˇka Vladimi´r , Reha´k Ivan
Published: April 2011

The computer code OMEGA was developed for evaluation and optimisation of decommissioning project planning. It implements the standardised cost structure PSL (Proposed Standardised List) developed by IAEA, OECD/NEA, EC [1], as the universal structure for calculation and optimisation of decommissioning scenarios. Dismantling of technological systems especially in radiation ambient is the most important among decommissioning activities.
Decommissioning Costing Approach Based on the Standardised List of Costing Items: Lessons Learnt by the OMEGA Computer Code
Authors: Danisˇka Vladimi´r , Reha´k Ivan , Vasˇko Marek , Ondra Frantisˇek , Beza´k Peter , Pri´trsky´ Jozef , Zachar Matej , Necˇas Vladimi´r
Published: April 2011

The document “A Proposed Standardised List of Items for Costing Purposes” [1] was issues in 1999 by OECD/NEA, IAEA and European Commission (EC) for promoting the harmonisation in decommissioning costing. It is a systematic list of decommissioning activities classified in chapters 01 to 11 with three numbered levels. Four cost groups are defined for cost at each level. Document constitutes the standardised matrix of decommissioning activities and cost groups with definition of content of items. Knowing what is behind the items makes the comparison of cost for decommissioning projects transparent. Two approaches are identified for use of the standardised cost structure. First approach converts the cost data from existing specific cost structures into the standardised cost structure for the purpose of cost presentation. Second approach uses the standardised cost structure as the base for the cost calculation structure; the calculated cost data are formatted in the standardised cost format directly; several additional advantages may be identified in this approach. The paper presents the costing methodology based on the standardised cost structure and lessons learnt from last ten years of the implementation of the standardised cost structure as the cost calculation structure in the computer code OMEGA. Code include also on-line management of decommissioning waste, decay of radioactivity, evaluation of exposure, generation and optimisation of the of the Gantt chart of a decommissioning project, which makes the OMEGA code an effective tool for planning and optimisation of decommissioning processes.
Environmental Remediation of High-Level Nuclear Waste in Geological Repository: Modified Computer Code Creates Ultimate Benchmark in Natural Systems
Authors: Peter Geoffrey J.
Published: April 2011

Isolation of high-level nuclear waste in permanent geological repositories has been a major concern for over 30 years due to the migration of dissolved radio nuclides reaching the water table (10,000-year compliance period) as water moves through the repository and the surrounding area. Repositories based on mathematical models allow for long-term geological phenomena and involve many approximations; however, experimental verification of long-term processes is impossible. Countries must determine if geological disposal is adequate for permanent storage. Many countries have extensively studied different aspects of safely confining the highly radioactive waste in an underground repository based on the unique geological composition at their selected repository location. This paper discusses two computer codes developed by various countries to study the coupled thermal, mechanical, and chemical process in these environments, and the migration of radionuclide. Further, this paper presents the results of a case study of the Magma-hydrothermal (MH) computer code, modified by the author, applied to nuclear waste repository analysis. The MH code verified by simulating natural systems thus, creating the ultimate benchmark. This approach based on processes similar to those expected near waste repositories currently occurring in natural systems.
Decontamination of Radioactive Concrete Wastes by Thermal and Mechanical Processes
Authors: Min Byung Youn , Choi Wang Kyu , Lee Ki Won , Lee Kune Woo , Chung Un Soo
Published: April 2011

The purpose of this paper is to provide the results of a series of volume reduction tests conducted in thermal and mechanical processes. The Korea Atomic Energy Research Institutes (KAERI) has developed volume reduction technology applicable to an activated heavy concrete waste generated by dismantling the South Korea Research Reactor (KRR-2) and the uranium-contaminated light weight concrete produced from a uranium conversion plant (UCP). The volume reduction rate could achieve above 70% by heating following a mechanical separation process. Demonstration tests were performed with concrete waste generated from KRR-2 and UCP by thermal and mechanical process. The developed processes were quite effective for the volume reduction of radioactively contaminated dismantled concrete waste.
Development of Requirements Management System of NUMO and Practical Experience With Development of the Database Contents
Authors: Suzuki Satoru , Ueda Hiroyoshi , Fujisaki Kiyoshi , Ishiguro Katsuhiko , Tsuchi Hiroyuki , Oyamada Kiyoshi , Yashio Shoko
Published: April 2011

Decision-making and work activities in the geological disposal program need to be implemented in such a way as to fulfill various requirements such as safety, engineering feasibility, quality and socio-economic aspects. Since a stepwise approach is applied for implementing the program, the number, weighting and specific nature of the requirements will change depending on the premises and constraints in each stage of implementation. Requirements management with a long-term perspective is therefore required for consistent implementation of the program. NUMO has developed a requirements management (RM) methodology that is suitable for the long-term, stepwise disposal program in Japan, as well as a supporting requirements management system (RMS) tool. The basic concept of the RMS was already presented at the last ICEM 2009. In this presentation, we will focus on practical experience with development of the database content for the RMS.
Status of the Support Researches for the Regulation of Nuclear Facilities Decommissioning in Japan
Authors: Masuda Yusuke , Iguchi Yukihiro , Kawasaki Satoru , Kato Masami
Published: April 2011

In Japan, 4 nuclear power stations are under decommissioning and some nuclear fuel cycle facilities are expected to be decommissioned in the future. On the other hand, the safety regulation of decommissioning of nuclear facilities was changed by amending act in 2005. An approval system after review process of decommissioning plan was adopted and applied to the power stations above. In this situation, based on the experiences of the new regulatory system, the system should be well established and moreover, it should be improved and enhanced in the future. Nuclear Industry and Safety Agency (NISA) is in charge of regulation of commercial nuclear facilities in Japan and decommissioning of them is included. Japan Nuclear Energy Safety Organization (JNES) is in charge of technical supports for NISA as a TSO (Technical Support Organization) also in this field. As for decommissioning, based on regulatory needs, JNES has been continuing research activities from October 2003, when JNES has been established. Considering the “Prioritized Nuclear Safety Research Plan (August 2009)” of the Nuclear Safety Commission of Japan and the situation of operators faculties, “Regulatory Support Research Plan between FY 2010–2014” was established in November 2009, which shows the present regulatory needs and a research program. This program consists of researches for 1. review process of decommissioning plan of power reactors, 2. review process of decommissioning plan of nuclear fuel cycle facilities, 3. termination of license at the end of decommissioning and 4. management of decommissioning waste. For the item 1, JNES studied safety assessment methods of dismantling, e.g. obtaining data and analysis of behavior of dust diffusion and risk assessment during decommissioning, which are useful findings for the review process. For the item 2, safety requirements for the decommissioning of nuclear fuel cycle facilities was compiled, which will be used in the future review. For the item 3, measuring method, release procedure and analysis code for the site release were studied for the establishment of the license termination process in the future. From FY 2010, based on the new plan, we have started the researches for the standardization of review process of decommissioning plan for power reactors and nuclear fuel cycle facilities, establishing the process and criteria of license termination and appropriate method of management of decommissioning waste based on the waste form confirmation process.
Design Options for HLW Repository Operation Technology: Part V—Preliminary Study and Small Scale Experiments on the Method of Removal of Buffer Material With Salt Solution
Authors: Toguri Satohito , Ishii Takashi , Jang Jiho , Okihara Mitsunobu , Iwasa Kengo , Nakashima Hitoshi , Asano Hidekazu
Published: April 2011

The Nuclear Safety Commission of Japan stipulates that “When closing a waste disposal site, the validity of safety assessment results should be verified using the data obtained in the construction and operation phases as well. The retrieval of high-level radioactive waste should be made continuously possible during the period before the verification of the validity.”[1] Retrieving high-level radioactive waste requires the removal of the bentonite-based buffer around the emplaced overpack. In this study, focus was placed on a method for reducing the cohesion of bentonite, a major component of the buffer by dipping the buffer in fluid salt solution and dissolving the material into a slurry using fluid salt solution for removal (method of making a slurry). In order to examine the feasibility and the basic characteristics of the method, element tests were conducted using a small specimen of buffer and fluid salt solution (NaCl solution). In order to verify the feasibility of the infiltration and jetting of fluid salt solution, small-scale model tests were conducted using a specimen composed of 1/14-scale overpack and buffer. It was made clear that the infiltration and jetting of fluid salt solution was feasible as a method for removing a buffer.
Integrated Strategy to Address Hanford’s Deep Vadose Zone Remediation Challenges
Authors: Triplett Mark B. , Freshley Mark D. , Truex Michael J. , Wellman Dawn M. , Gerdes Kurt D. , Charboneau Briant L. , Morse John G. , Lober Robert W. , Chronister Glen B.
Published: April 2011

A vast majority of Hanford’s remaining in-ground contaminants reside in the vadose zone of the Central Plateau, where reprocessing operations occurred. The vadose zone is comprised of about 75 meters of water-unsaturated sediments above groundwater. If left untreated, these contaminants could reach groundwater and could remain a threat for centuries. Much of this contamination resides deep in the vadose zone, below the effective depth of tradition surface remedy influence. In 2008, the Department of Energy initiated deep vadose zone treatability testing to seek remedies for technetium-99 and uranium contamination. These tests include the application of desiccation for technetium-99 and reactive gas technologies for uranium. To complement these efforts, the Department of Energy has initiated a “defense-in-depth” approach to address the unique challenges for characterization and remediation of the deep vadose zone. This defense-in-depth approach will implement multiple approaches to understand and control contaminant flux from the deep vadose zone to the groundwater. Among these approaches is an increased investment in science and technology solutions to resolve deep vadose zone challenges including characterization, prediction, remediation, and monitoring.
TRU Recycling Options for Environmentally Friendly and Proliferation-Resistant Nuclear Fuel Cycle of FBR
Authors: Permana Sidik , Suzuki Mitsutoshi
Published: April 2011

The embodied challenges for introducing closed fuel cycle are utilizing advanced fuel reprocessing and fabrication facilities as well as nuclear nonproliferation aspect. Optimization target of advanced reactor design should be maintained properly to obtain high performance of safety, fuel breeding and reducing some long-lived and high level radioactivity of spent fuel by closed fuel cycle options. In this paper, the contribution of loading trans-uranium to the core performance, fuel production, and reduction of minor actinide in high level waste (HLW) have been investigated during reactor operation of large fast breeder reactor (FBR). Excess reactivity can be reduced by loading some minor actinide in the core which affect to the increase of fuel breeding capability, however, some small reduction values of breeding capability are obtained when minor actinides are loaded in the blanket regions. As a total composition, MA compositions are reduced by increasing operation time. Relatively smaller reduction value was obtained at end of operation by blanket regions (9%) than core regions (15%). In addition, adopting closed cycle of MA obtains better intrinsic aspect of nuclear nonproliferation based on the increase of even mass plutonium in the isotopic plutonium composition.
Main Results of a Remediation of Uranium- and CHC-Contaminated Groundwater
Authors: Wo¨rner Jo¨rg , Margraf Sonja , Hackel Walter
Published: April 2011

Since July 2002 a pump & treat remedial action has been in operation for the extraction of Uranium- and “CHC-compounds” contaminated water flowing in the ground of a formerly used industrial site where nuclear fuel elements were produced. Meanwhile about 21 kg Uranium and 28 kg CHC-compounds have been eliminated. Two ground-water plumes have transported the dissolved Uranium down-stream to locations where two main remediation-wells were in use for most of the remediation-time. They showed characteristic kinetic differences with respect to their U-nuclide vector from the very beginning. A meanwhile additionally close-by set well influenced that observation so that the formerly used two wells were assimilated gradually due to their relatively downstream position. Almost 300,000 m3 ground-water of the overall 440,000 m3 have been pumped therefrom. The second area’s remediation started in-between not being affected by the first plume’s aquifer. This observed assimilation is the result of intensive ground-water blending when the two plumes’ waters penetrate in a specific area by flowing within preferred aquifer’s paths. The first plume’s water characterized by decreasing Uranium-235 ratios is meanwhile dominated by the second plume’s water of up to 90% in case of the two elder wells. The overall activity of 132 MBq Uranium-235 has been extracted from the aquifer. Only a small area remains where the extraction of the first plume’s pure ground-water was started in 2009. The progress of the two plumes’ remediation is described by reporting the Uranium- and CHC-results of all wells. Nevertheless both target values of 20 μg/l and 10 μg/1 for dissolved Uranium and CHC-compounds, respectively, could not yet be reached for all remediation wells. In accordance to the 10μSv-concept of radiation protection the activity parameters have to be improved still in order to release the complete site from the German Atomic Law.
Automated Intelligent Emergency Assessment of GTA Pipeline Events
Authors: Asgary Ali , Ghaffari Alireza , Kong Albert
Published: April 2011

The risks to the local population, infrastructure and the environment posed by fluid spills associated with oil and gas pipelines running throughout the Greater Toronto Area (GTA) are evaluated using fuzzy inference rules encoded using JESS and fuzzy J. The evaluation uses data obtained in real time from web services, such as weather, Geographic Information Systems (GIS), for example, distances of event from emergency services and Supervisory Control and Data Acquisition (SCADA) systems, where available. These risks are diverse depending on the local infrastructure or lack thereof (in the case of the environment) indicated by the zoning of the area of the spill, population densities and other factors. The application uses an advanced Human Machine Interface (HMI) accessible via Hypertext Transfer Protocol (HTTP) from anywhere on the Web. It is intended to support decision making in emergency response scenarios.
Pipeline Geo-Hazard Prediction and Early Warning During Summer Monsoon Based on GIS Technology
Authors: Jia Shaohui
Published: April 2011

In annual summer monsoon, geo-hazard is common. Monsoon-caused casualties and economic losses throughout the year accounted for 70% ∼ 80% of the total annual losses. Also, geo-hazard is a serious threat for pipeline operators to manage. Over 12,000 kilometers of pipelines with crude oil, gas, and refined oil are operated by PetroChina Pipeline Company. The pipelines, through sixteen provinces and cities, have been operated for over forty years. Geographic Information System (GIS) technology, as an effective spatial analysis tool, provides advanced analysis for pipeline geo-hazard prediction and early warning during summer monsoon based on field data and historical precipitation records. After many years of research and applicaton of our prediction model of pipeline geo-hazard, an important link between geo-hazard and rainfall is understood. Rainfall is the main triggering factor of geo-hazards such as landslide and debris flow leading to heavy losses, especially rainstorm and heavy rainstorm. We use GIS technology to perform spatial analysis with predicted rainfall data the next twenty-four hours and the data of pipeline geo-hazard susceptibility, and predict the severity of pipeline impacts caused by geo-hazards during the next twenty-four hours. Finally, the result is modified by existed geo-hazards data. The pipeline geo-hazard early warning is divided into five ranks which are displayed by different colors, and pipelines damaged by geo-hazards and protection measures are also proposed. During July 16 and 17 of 2009 years, we released geo-hazard early warning four rank of Lanzhou-Chengdu-Chongqing Oil Pipeline through PetroChina Pipeline Company web page (http://www.gdgs.petrochina) and the communication software of IM. The Lanzhou-Chengdu-Chongqing Oil Pipeline Company acted promptly with a detailed deployment and emergency plan to ensure pipeline safety.
Finite-Element Model-Based Fault Prognosis on Key Components of the Reciprocating Compressor
Authors: Lu Wenqing , Zhang Laibin , Liang Wei , Li Shuguo
Published: April 2011

The reciprocating compressor has become one of the most important equipments in petroleum and chemical industry. Study on vibration of the reciprocating compressor has a great significance to monitor the safety and reliability of the compressor. But it’s very difficult to predict the compressor and achieve the desired goal due to the complicated structure and operational aspect of the compressor. Experimental solution is expensive and time consuming. Therefore, finite element analysis (FEA) method is proposed to predict and locate the breakage of several key components on reciprocating compressor in compressor station. Non-destructive fault diagnosis and troubleshooting of the compressor can be achieved by application of FEA. The reasonable and simplified 3D model of the reciprocating compressor, which is validated with the actual prototype, is built by a CAD drawing software-SolidWorks. Then the ANSYS FE model is created by importing the 3D model into a FEA software-ANSYS. The ANSYS FE model can be used for stress analysis as well as intrinsic property analysis of the structural components. In this paper there are several ANSYS FE models of key components presented, including crankshaft, connecting-rod, crosshead and air valve. Then FEA method is applied to the fault localization of those components. According to the simulation results, the sites vulnerable to failure can be fixed on key components. The conclusions are consistent with the problems during the normal operation. Therefore, FEA is an effective and prospective method on fault prognosis of the reciprocating compressor.
Meeting the Geohazards Management Guidelines of Annex N
Authors: Zaleski Martin , Greaves Tom , Bracic Jan
Published: April 2011

The Canadian Standards Association’s Publication Z662-07, Annex N provides guidelines for pipeline integrity management programs. Government agencies that regulate pipelines in Alberta, British Columbia and other Canadian jurisdictions are increasingly using Annex N as the standard to which pipeline operators are held. This paper describes the experience of Pembina Pipeline Corporation (Pembina) in implementing a geohazards management program to fulfill components of Annex N. Central to Pembina’s program is a ground-based inspection program that feeds a geohazards database designed to store geotechnical and hydrotechnical site information and provide relative rankings of geohazard sites across the pipeline network. This geohazard management program fulfills several aspects of the Annex, particularly: record keeping; hazard identification and assessment; risk assessment and reduction; program planning; inspections and monitoring; and mitigation. Pembina’s experience in growing their geohazard inventory from 65 known sites to over 1300 systematically inspected and catalogued sites in a span of approximately two years is discussed. Also presented are methods by which consultants and Pembina personnel contribute to the geohazard inspection program and geohazard inventory, and how the ground inspection observations trigger follow-up inspections, monitoring and mitigation activities.
Response of Buried Plastic Pipelines Subject to Lateral Ground Movement
Authors: Weerasekara Lalinda , Wijewickreme Dharma
Published: April 2011

The performance of pipelines in areas prone to ground deformations is a major concern for utility owners since the failures of such pipeline systems could cause property damage and even human losses, in addition to business disruption. An analytical solution to determine the response of plastic pipelines subject to abrupt relative ground movement occurring perpendicular to the pipe axis is presented herein. The method accounts for the combined impacts of tension and bending in a pipe segment. Furthermore, the model considers the nonlinear stress-strain behavior of the pipe material and employs an advanced analytical model to calculate the frictional force development along the pipeline. The results obtained from this analytical approach are validated by comparing with the results obtained from a numerical model using soil-spring analysis and the actual viscoelastic material behavior for the pipe material.
A Study of Cases of Hydrostatic Tests Where Multiple Test Failures Have Occurred
Authors: Kiefner John F. , Kolovich Kolin M. , Kariyawasam Shahani
Published: April 2011

The retesting of pipelines for integrity management purposes often involves testing of pipelines where multiple test failures can be expected. Multiple failures are most likely to occur when an existing pipeline is tested to a hoop stress level in excess of those used in prior tests of the pipeline. A major cause of such failures is seam manufacturing defects, but other types of defects such as mechanical damage or stress corrosion cracking may cause numerous failures as well. The occurrence of multiple failures can be costly in terms of the time the pipeline must remain out of service. Multiple failures sometimes involve pressure reversals that may affect confidence in the level of integrity sought by the pipeline operator. The study described in this paper involved a review of five actual cases of hydrostatic tests where multiple test failures occurred. On the basis of these cases a method was developed for predicting the ultimate number of failures required to reach a desired test level from the pressure levels of the first few failures. In addition, an improved method for estimating the probability of a pressure reversal of a given size was developed. Pipeline operators could use these techniques to decide when to terminate a hydrostatic test and to assess the effectiveness of the test in terms of a level of confidence that an integrity-threatening pressure reversal will not occur.
Experimental Testing and Evaluation of Crack Defects in Line Pipe
Authors: Hosseini Ali , Cronin Duane , Plumtree Alan , Kania Richard
Published: April 2011

Pipelines are in wide use throughout the world, and aging pipelines may experience defects such as environmental or stress-induced cracking. The evaluation of crack defects is important for continued safe operation of pipelines. At present, there are several assessment methods for crack-like defects in pipelines including API579, BS 7910, NG18, software applications, as well as numerical modeling approaches. All have been used successfully to evaluate crack defects, but the degree of conservatism and sensitivity to the various input parameters is not known. To address this need, a series of full-scale burst tests was undertaken on end-capped, seam-welded pipe specimens. The tests were carried out on 508 mm (20 inch) diameter Grade API 5L X60 line pipe with a 5.7 mm wall thickness. Elliptical cracks were created by first cutting a longitudinally oriented narrow slit in each pipe and then pre-fatiguing the pipes to create sharp cracks of different depths. Rupture tests were conducted by pressurizing the pipes to failure and the failure pressure was evaluated using current assessment methods. Examination of the fracture surface showed that the pipe sections failed by ductile tearing, as expected for the material and crack sizes. It was found that the Level 3 FAD for API 579 (J approach, using the cylinder equations) and CorLAS provided the most accurate prediction in comparison with the other methods i.e. BS7910 and NG-18.