Gamma Spectrometry Systems for the Assay of Uranium Residues and Potentially Contaminated Low Level Wastes at the Capenhurst Site

2003 ◽  
Author(s):  
P. A. Clark ◽  
D. F. Parvin ◽  
C. Y. Powrie ◽  
C. H. Orr ◽  
G. Mottershead ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Matrix Correction ◽  
Uranium Recovery ◽  
Measurement Systems ◽  
Low Level ◽  
Fuel Fabrication ◽  
Wide Range ◽  
Contaminated Waste ◽  
The Uk ◽  
High Level

BNFL has produced and operates a wide range of DrumScan® gamma measurement systems for monitoring packages, drums and boxed wastes arising from nuclear power plant reprocessing, fuel fabrication and decommissioning operations. The challenges associated with decommissioning operations are met by employing a range of technologies predominantly High Resolution and Low Resolution spectrometry (HRGS & LRGS). This paper describes how BNFL Instruments’ LRGS and HRGS DrumScan® gamma measurement systems have been used for the assay of uranium resides and potentially contaminated low level wastes by Capenhurst Integrated Decommissioning Project (IDP) in the UK. A description of the two Capenhurst segmented HRGS systems is included. Whilst Segmented Gamma Scanning is a well established technique for the non-destructive assay of gamma emitting radioisotopes in drummed waste, these systems utlise unique features to address the specific measurement requirements. The first system is configured for the accurate measurement of both small sized containers of uranium residues arising from recovery operations and low level wastes potentially contaminated with uranium contained in 200 litre drums. To achieve a high level of accuracy, this system uses a novel mechanical arrangement to overcome the wide variety of container sizes, and the unique “TransWeight” and “Transmission” matrix correction techniques which provide significant improvements over conventional Segmented Gamma Scanner matrix correction techniques. The second system is configured for Nuclear Safety purposes to provide an upper limit of the 235U present in 200 litre drums of potentially contaminated waste prior to the opening of the drums for sorting and uranium recovery operations. This system is configured to report an appropriately pessimistic upper estimate of the 235U present. A brief description of the LRGS systems used by Capenhurst is also provided. These systems have served to quantify the 235U content within a variety of potentially contaminated waste items ranging from 200 litre drums to 1m3 boxed waste.

The Benefits of Cementitious Encapsulation Matrices for the Conditioning of Intermediate Level Waste

2003 ◽  
Author(s):  
R. M. Guppy ◽  
S. P. Vines ◽  
S. J. Wisbey
Keyword(s):  
Nuclear Power ◽  
Raw Materials ◽  
Chemical Diversity ◽  
Intermediate Level ◽  
Quality Data ◽  
Extensive Experience ◽  
Wide Range ◽  
The Uk ◽  
High Level ◽  
Interim Storage

The UK has significant quantities of radioactive waste, which have arisen over the past fifty years or so, largely as a result of nuclear power, reprocessing and defence programmes. The intermediate level wastes arising as a result of these activities, exhibit a high level of physical and chemical diversity, and must be managed safely in a way that protects existing and future generations and the environment. Development work has been conducted since the early 1980s to identify suitable conditioning materials and techniques that are compatible with the needs of safe long-term management, including interim storage, transport and future deep geological disposal. From these studies cementation emerged as the one medium which could satisfy all the key waste management criteria. Other materials were not ruled out and may offer benefits in specific applications. The advantages of conditioning ILW with cement include: • the extensive experience of its use in a wide variety of contexts; • the raw materials are relatively cheap and have a long shelf life; • cement is processed in relatively simple plant at room temperature, with safety and cost benefits for plant operators; • the product is fire resistant and of relatively low toxicity; • cement is capable of immobilising a wide range of wastes ranging from solids to aqueous slurries; • cement provides desirable product properties. Desirable properties include: • suitable strength, • chemical control of radionuclide leading to enhanced retention, • good corrosion protection for steels, • low permeability, • tolerance to radiation, • durability over extended timescales, and • good radiation self-shielding properties. Several waste packaging plants are now operational in the UK using cement-based encapsulants. These are currently conditioning ILW for interim storage, in a manner suitable for future transport and compatible with the Nirex phased deep disposal concept. This paper will describe the development of cement-based encapsulants to meet the needs of UK radioactive wastes, and will provide examples of the supporting product quality data.

Comparative Study Dynamics of Psychology of Pencak Silat Groups (Iks.Pi Kera Sakti, Persaudaraan Setia Hati Terate, Dan Pagarnusa)

2013 ◽  
Vol 1 (1) ◽  
pp. 114-119
Author(s):  
Imam Muzakky ◽  
Dwi Umi Novitasari ◽  
Siti Hamidah
Keyword(s):  
Comparative Study ◽  
Research Methods ◽  
Martial Arts ◽  
Quantitative Approach ◽  
High Type ◽  
Tolerance Level ◽  
Low Level ◽  
Empirical Paper ◽  
Wide Range ◽  
High Level

Indonesia as a country that offers a wide range of diversity offers its own uniqueness. But unfortunately the diversity it also has the potential for conflict ( Rahardjo , 2010) . Not only the conflict between cultures and groups, as happened in intercollegiate martial arts such as pagarnusa, PSHT and Kerasakti. Objective The purpose of this study to determine the level of aggressiveness, collective pride and tolerance in three martial arts college , this is one of the factors of conflict is high aggressiveness, collective pride and a low level of tolerance. Methodology/Technique The study involved 30 members pagarnusa , 30 members and 30 members kerasakti PSHT . Research methods with quantitative approach. Findings – The findings of this study are a group of college kerasakti have the highest tolerance, low aggression and collective pride being. PSHT has a high level of aggressiveness being and collective tolerance pride being, while the pagarnusa Group aggressiveness levels that are low tolerance level and collective pride high. Findings The findings of this study are a group of college kerasakti have the highest tolerance, low aggression and collective pride being. PSHT has a high level of aggressiveness being and collective tolerance pride being, while the pagarnusa Group aggressiveness levels that are low tolerance level and collective pride high. Type of Paper Empirical paper Keywords: Martial Arts, Aggressiveness, Tolerance , Collective Pride

Brian Eyre CBE FREng. 29 November 1933 — 28 July 2014

2016 ◽  
Vol 62 ◽  
pp. 147-166
Author(s):  
Derek Pooley ◽  
George Smith ◽  
Colin Windsor
Keyword(s):  
Nuclear Power ◽  
Chief Executive ◽  
Structural Components ◽  
Theoretical Understanding ◽  
Leading Role ◽  
Void Swelling ◽  
Intergranular Embrittlement ◽  
Wide Range ◽  
East End ◽  
The Uk

Brian Eyre was an outstanding metallurgist who played a leading role in the development of nuclear engineering materials. His experiments on irradiated metals enabled a theoretical understanding of the mechanisms of radiation damage, and in particular the formation of voids and void swelling in structural steels. His work on the fracture of metals advanced our understanding of intergranular embrittlement and helped define the specifications of the structural components in nuclear reactors. He rose from a humble upbringing in London's East End to become Chief Executive of the UK Atomic Energy Authority (UKAEA). He was instrumental in transforming the UKAEA from a organization whose mission was to develop nuclear power generating systems into the privatized AEA Technology, which worked on a wide range of technologies on a customer–contractor basis.

scholarly journals Opportunities and Challenges for Structural Health Monitoring of Radioactive Waste Systems and Structures

2013 ◽  
Author(s):  
Victor Giurgiutiu ◽  
Adrián E. Méndez Torres
Keyword(s):  
Structural Health Monitoring ◽  
Radioactive Waste ◽  
Nuclear Fuel ◽  
Health Monitoring ◽  
Nuclear Power ◽  
High Level Radioactive Waste ◽  
Structural Health ◽  
Used Nuclear Fuel ◽  
Wide Range ◽  
High Level

Radioactive waste systems and structures (RWSS) are safety-critical facilities in need of monitoring over prolonged periods of time. Structural health monitoring (SHM) is an emerging technology that aims at monitoring the state of a structure through the use of networks of permanently mounted sensors. SHM technologies have been developed primarily within the aerospace and civil engineering communities. This paper addresses the issue of transitioning the SHM concept to the monitoring of RWSS and evaluates the opportunities and challenges associated with this process. Guided wave SHM technologies utilizing structurally-mounted piezoelectric wafer active sensors (PWAS) have a wide range of applications based on both propagating-wave and standing-wave methodologies. Hence, opportunities exist for transitioning these SHM technologies into RWSS monitoring. However, there exist certain special operational conditions specific to RWSS such as: radiation field, caustic environments, marine environments, and chemical, mechanical and thermal stressors. In order to address the high discharge of used nuclear fuel (UNF) and the limited space in the storage pools the U.S. the Department of Energy (DOE) has adopted a “Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste” (January 2013). This strategy endorses the key principles that underpin the Blue Ribbon Commission’s on America’s Nuclear Future recommendations to develop a sustainable program for deploying an integrated system capable of transporting, storing, and disposing of UNF and high-level radioactive waste from civilian nuclear power generation, defense, national security, and other activities. This will require research to develop monitoring, diagnosis, and prognosis tools that can aid to establish a strong technical basis for extended storage and transportation of UNF. Monitoring of such structures is critical for assuring the safety and security of the nation’s spent nuclear fuel until a national policy for closure of the nuclear fuel cycle is defined and implemented. In addition, such tools can provide invaluable and timely information for verification of the predicted mechanical performance of RWSS (e.g. concrete or steel barriers) during off-normal occurrence and accident events such as the tsunami and earthquake event that affected Fukushima Daiichi nuclear power plant. The ability to verify the conditions, health, and degradation behavior of RWSS over time by applying nondestructive testing (NDT) as well as development of nondestructive evaluation (NDE) tools for new degradation processes will become challenging. The paper discusses some of the challenges associated to verification and diagnosis for RWSS and identifies SHM technologies which are more readily available for transitioning into RWSS applications. Fundamental research objectives that should be considered for the transition of SHM technologies (e.g., radiation hardened piezoelectric materials) for RWSS applications are discussed. The paper ends with summary, conclusions, and suggestions for further work.

scholarly journals Implementation of integrated design space exploration of scheduling, allocation and binding in high level synthesis using multi structure genetic algorithm

2021 ◽  
Author(s):  
Michael Gebremariam
Keyword(s):  
Genetic Algorithm ◽  
Design Space Exploration ◽  
Design Space ◽  
Space Exploration ◽  
Integrated Design ◽  
High Level Synthesis ◽  
C Language ◽  
Low Level ◽  
Wide Range ◽  
High Level

The objective of this project is to develop a software tool which assists in comparison of a work known as "M-GenESys: Multi Structure Genetic Algorithm based Design Space Exploration System for Integrated Scheduling, Allocation and Binding in High Level Synthesis" with another well established GA approach known as "A Generic Algorithm for the Design Space Exploration of Data paths During High-Level Synthesis". Two sets of software are developed based on both approaches using Microsoft Visual 2005 C# language. The C# language is an object-oriented language that is aimed at enabling programmers to quickly develop a wide range of applications on the Microsoft .NET platform. The goal of C# and the .NET platform is to shorten development time by freeing the developer from worrying about several low level plumbing issues such as memory equipment, type safety issues, building low level libraries, array bound checking, etc., thus allowing developers to actually spend their time and energy working on the application and business logic.

Building the UK ABWR: Developments in Structural Integrity Safety Cases for Highest Reliability Components in the UK

2018 ◽  
Author(s):  
Tim Jelfs ◽  
James O’Neill ◽  
Angus Beveridge
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Structural Integrity ◽  
Advisory Group ◽  
Manufacturing Processes ◽  
Design And Manufacturing ◽  
Safety Case ◽  
Safety Cases ◽  
The Uk ◽  
High Level

Nuclear power plants contain certain components whose gross failure would lead to intolerable radiological consequences. In the UK, a common terminology used for such components is Very High Integrity (VHI). If it is not possible to engineer lines of protection for these components, a safety case must demonstrate to UK regulators that the probability of gross failure is demonstrably so low that it can be discounted. A previous paper [Ref. 1] has described, at a high level, how the structural integrity safety case for a nuclear new build project in the UK — the UK Advanced Boiling Water Reactor (UK ABWR) is being structured. As described in [Ref. 1], the structural integrity safety case for the UK ABWR is based on the guidance provided by the UK Technical Advisory Group on Structural Integrity (TAGSI) and aims to demonstrate a multi-legged safety case with robust and independent legs giving confidence of defense in depth. Design to the internationally recognized ASME code [Refs. 2, 3, 4] is supplemented by a significant number of beyond code requirements such as supplementary inspection and inspection qualification, augmented material testing requirements, defect tolerance assessment to the well-established R6 procedure [Ref. 5], and demonstration that design and manufacturing processes have reduced risks to As Low as Reasonably Practicable (ALARP). This paper provides an updated position of the progress made on the UK ABWR project. It also provides more specific details on the activities the future licensee, Horizon Nuclear Power, has performed in support of the demonstration that design and manufacturing processes have reduced risks to ALARP. This kind of additional work is vital to providing the UK regulator with confidence that the risk of failure of VHI components has been reduced to ALARP.

Self-Care Activities among People with Multiple Sclerosis in Denmark: Use and User Characteristics

2017 ◽  
Vol 24 (4) ◽  
pp. 240-245
Author(s):  
Marie Lynning ◽  
Kirsten Hanehøj ◽  
Astrid Karnøe Knudsen ◽  
Lasse Skovgaard
Keyword(s):  
Multiple Sclerosis ◽  
Online Survey ◽  
Self Care ◽  
Primary Source ◽  
User Characteristics ◽  
Cross Sectional ◽  
Low Level ◽  
Wide Range ◽  
Cross Sectional Design ◽  
High Level

Background: People with multiple sclerosis (PwMS) are known to use a wide range of medical and non-medical treatments. This study aims at investigating the use of self-care activities within this patient group. Material and Methods: The study follows a descriptive cross-sectional design based on an online survey among members of the Danish Multiple Sclerosis Society's permanent respondent panel. Results: The results of the study indicate that the respondents carry out a wide variety of self-care activities. These activities comprise conventional activities as well as complementary and alternative medicine (CAM)-based activities. The self-care activities are mainly kept up for non-specific and preventive purposes, with primarily personal or non-specific issues as the primary source of inspiration. Comparative analyses indicate that respondents with a low level of self-care more often are men, belong to the young age group and have a low level of education, a low level of self-assessed state of health, a low level of self-assessed quality of life (QoL), and an unknown subdiagnosis. Respondents with a high level of self-care are more often women and have a high level of self-assessed QoL. Conclusions: A wide variety of self-care activities are carried out by PwMS, comprising conventional as well as CAM-based activities. The purposes of such activities are manifold, but they are mainly of non-specific and preventive nature. Differences in background characteristics exist between groups of low and high levels of self-care.

scholarly journals CTF and FLOCAL Thermal Hydraulics Validations and Verifications within a Multiscale and Multiphysics Software Development

Energies ◽  
2021 ◽  
Vol 14 (5) ◽  
pp. 1220
Author(s):  
Sebastian Davies ◽  
Ulrich Rohde ◽  
Dzianis Litskevich ◽  
Bruno Merk ◽  
Paul Bryce ◽  
...  
Keyword(s):  
Software Development ◽  
Turbulent Mixing ◽  
Nuclear Power ◽  
Nuclear Reactor ◽  
Journal Article ◽  
Thermal Hydraulics ◽  
Reactor Physics ◽  
Wide Range ◽  
The Uk ◽  
Simulation Codes

Simulation codes allow one to reduce the high conservativism in nuclear reactor design improving the reliability and sustainability associated with nuclear power. Full-core coupled reactor physics at the rod level are not provided by most simulation codes. This has led in the UK to the development of a multiscale and multiphysics software development focused on LWRS. In terms of the thermal hydraulics, simulation codes suitable for this multiscale and multiphysics software development include the subchannel code CTF and the thermal hydraulics module FLOCAL of the nodal code DYN3D. In this journal article, CTF and FLOCAL thermal hydraulics validations and verifications within the multiscale and multiphysics software development have been performed to evaluate the accuracy and methodology available to obtain thermal hydraulics at the rod level in both simulation codes. These validations and verifications have proved that CTF is a highly accurate subchannel code for thermal hydraulics. In addition, these verifications have proved that CTF provides a wide range of crossflow and turbulent mixing methods, while FLOCAL in general provides the simplified no-crossflow method as the rest of the methods were only tested during its implementation into DYN3D.

scholarly journals GPU implementation of restricted Boltzmann machines with application to view classification in sports videos

2021 ◽  
Author(s):  
Andreas Fred Bernitzke
Keyword(s):  
Genetic Algorithm ◽  
Design Space Exploration ◽  
Design Space ◽  
Space Exploration ◽  
High Level Synthesis ◽  
Restricted Boltzmann Machines ◽  
C Language ◽  
Low Level ◽  
Wide Range ◽  
High Level

The objective of this project is to develop a software tool which assists in comparison of a work known as "M-GenESys: Multi Structure Genetic Algorithm based Design Space Exploration System for Integrated Scheduling, Allocation and Binding in High Level Synthesis" with another well established GA approach known as "A Genetic Algorithm for the Design Space Exploration of Data paths During High-Level Synthesis". Two sets of Software are developed based on both approaches using Microsoft visual 2005,C# language. The C# language is an object-oriented language that is aimed at enabling programmers to quickly develop a wide range of applications on the Microsoft .NET platform. The goal of C# and the .NET platform is to shorten development time by freeing the developer from worrying about several low level plumbing issues such as memory management, type safety issues, building low level libraries, array bounds checking, etc. thus allowing developers to actually spend their time and energy working on the application and business logic.

scholarly journals Challenges of SMR Licensing Practices

2012 ◽  
Vol 1 (2) ◽  
pp. 19-31 ◽  
Author(s):  
K. Söderholm
Keyword(s):  
Nuclear Power ◽  
Public Information ◽  
Lessons Learned ◽  
Point Of View ◽  
Aviation Industry ◽  
Small Modular Reactor ◽  
The Usa ◽  
Serial Construction ◽  
The Uk ◽  
High Level

This paper aims to increase the understanding of high level Nuclear Power Plant (NPP) licensing processes in Finland, France, the UK, Canada and the USA. These countries have been selected for this study because of their different licensing processes and recent actions in new NPP construction. After discussing their similarities and differences, suitable features for Small Modular Reactor licensing can be emphasized and suggested. Some of the studied licensing processes have elements that are already quite well suited for application to SMRs, but all of these different national processes can benefit from studying and implementing lessons learned from SMR specific licensing needs. The main SMR features to take into account in licensing are standardization of the design, modularity, mass production and serial construction. Modularity can be divided into two different categories: the first category is simply a single unit facility constructed of independently engineered modules (e.g., construction process for Westinghouse AP-1000 NPP) and the second is a facility structure composed of many reactor modules where modules are manufactured in factories and installed into the facility as needed (e.g., NuScale Power SMR design). Short construction schedules will not be fully benefitted from if the long licensing process prolongs the commissioning and approach to full-power operation. The focus area of this study is to better understand the possibility of SMR deployment in small nuclear countries, such as Finland, which currently has four operating NPPs. The licensing process needs to be simple and clear to make SMR deployment feasible from an economical point of view. This paper uses public information and interviews with experts to establish the overview of the different licensing processes and their main steps. A high-level comparison of the licensing steps has been carried out. Certain aspects of the aviation industry licensing process have also been studied and certain practices have been investigated as possibly suitable for use in nuclear licensing. All of the current licensing processes were found to be quite heavy and time-consuming and further streamlining could be possible without compromising safety or the need for public participation in the licensing process. Some examples of the modification possibilities for SMR applications are discussed. A profound discussion on SMR-specific licensing models, and on ways to simplify and harmonize them, will be needed in the near future in Europe too. This would be a natural continuation to the harmonization efforts underway for existing and new large reactors.

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