A5012815955- Nuclear reactor physics and engineering
- Nuclear Physics and Applications
- Nuclear Materials and Properties
- Nuclear physics research studies
- Graphite, nuclear technology, radiation studies
- Cooperative Communication and Network Coding
- Advanced Data Compression Techniques
- Fusion materials and technologies
- Radioactive contamination and transfer
- Wireless Communication Security Techniques
- Algorithms and Data Compression
- Nuclear and radioactivity studies
- Error Correcting Code Techniques
- Nuclear Engineering Thermal-Hydraulics
- Neutrino Physics Research
- Magnetic confinement fusion research
- Data Quality and Management
- Energy Harvesting in Wireless Networks
- Communication in Education and Healthcare
- Blind Source Separation Techniques
- Innovative Teaching and Learning Methods
- Transcranial Magnetic Stimulation Studies
- Radioactive Decay and Measurement Techniques
- Digital Humanities and Scholarship
- Historical and Literary Studies
Nuclear Energy Agency
2018-2024
University of Glasgow
2024
International Atomic Energy Agency
2020
United Kingdom Atomic Energy Authority
2016-2019
Culham Science Centre
2016-2019
Culham Centre for Fusion Energy
2016-2018
King's College London
2014-2017
Columbia University
2016
University of Cambridge
2016
California Institute of Technology
1999-2006
Abstract The joint evaluated fission and fusion nuclear data library 3.3 is described. New evaluations for neutron-induced interactions with the major actinides $$^{235}\hbox {U}$$ <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML"><mml:mrow><mml:msup><mml:mrow /><mml:mn>235</mml:mn></mml:msup><mml:mtext>U</mml:mtext></mml:mrow></mml:math> , $$^{238}\hbox /><mml:mn>238</mml:mn></mml:msup><mml:mtext>U</mml:mtext></mml:mrow></mml:math> $$^{239}\hbox {Pu}$$...
We present an algorithm for designing locally optimal vector quantizers general networks. discuss the algorithm's implementation and compare performance of resulting "network quantizers" to traditional (VQs) rate-distortion (R-D) bounds where available. While some special cases network codes (e.g., multiresolution (MR) multiple description (MD) codes) have been studied in literature, we here a unifying approach that both includes these existing solutions as provides previously unsolved examples.
The TALYS Evaluated Nuclear Data Library (TENDL) has now 8 releases since 2008. Considerable experience been acquired for the production of such general-purpose nuclear data library based on feedback from users, evaluators and processing experts. backbone this achievement is simple robust: completeness, quality reproducibility. If TENDL extensively used in many fields applications, it necessary to understand its strong points remaining weaknesses. Alternatively, essential knowledge not...
Packet-based data communication systems suffer from packet loss under high network traffic conditions. As a result, the receiver is often left with an incomplete description of requested data. Multiple source coding addresses problem minimizing expected distortion caused by loss. An equivalent that for transmission over multiple channels where each channel has some probability breaking down. Recent work in practical explores design scalar and vector quantizers case two or packets. This paper...
The challenge for any nuclear data evaluation project is to periodically release a revised, fully consistent and complete library, with all needed covariances, ensure that it robust reliable variety of applications. Within an effort, benchmarking activities play important role in validating proposed libraries. Joint Evaluated Fission Fusion (JEFF) Project aims provide such thus, requires coherent efficient process. aim this paper present the carried out by new JEFF Benchmarking Validation...
The OECD-NEA High Priority Request List (HPRL) is a point of reference to guide and stimulate the improvement nuclear data for energy other applications, tool bridge gap between users producers. HPRL application-driven requests are submitted by or representatives user’s communities. A panel international experts reviews monitors in framework an Expert Group mandated NEA Nuclear Science Committee Working Party on International Data Evaluation Cooperation (WPEC). After approval, individual...
The FISPACT-II inventory simulation platform is a modern computational tool with advanced and unique capabilities. It sufficiently flexible efficient to make it an ideal basis around which perform extensive studies scope variety of responses many materials (elements) several different neutron irradiation scenarios. This paper briefly presents the typical outputs from these scoping studies, have been used compile suite nuclear physics handbooks, providing useful vital resource for material...
In this correspondence, we consider rate-distortion examples in the presence of side information. For a system with some information known at both encoder and decoder, only evaluate rate distortion function for Gaussian binary sources. While example is straightforward generalization corresponding result by Wyner, proves more difficult solved using multidimensional optimization approach. Leveraging insights gained from example, then solve complicated Heegard Berger problem decoding when may...
A network source code is an optimal for a network. To design codes, we require each node to have single encoder, which jointly encodes all messages transmitted by that node, and decoder, decodes arriving at node. Given distribution over the sources, of optimizes encoders decoders obtain best performance with respect user-defined priority schedule rates distortions system. In this paper focus on fixed-rate codes address implementation existing algorithm vector quantizers. Implementing not...
The Working Party on International Nuclear Data Evaluation Co-operation Subgroup 47 (WPECSG47) entitled "Use of Shielding Integral Benchmark Archive and Database for Validation" was organised from 2019 2022 with the objectives to promote more systematic wider use shielding benchmark experiments in nuclear data (ND) transport code validation development, provide feedback (SINBAD), its further development coordination Expert Group Physics Reactor Systems (EGPRS). Altogether 9 meetings, large...
The JEFF library does not contain fission yield covariances, but simply best estimates and uncertainties. This situation is unique as all libraries are facing this deficiency, firstly due to the lack of a defined format. An alternative approach provide set random yields, themselves reflecting covariance information. In work, these files obtained combining information from (fission yields uncertainties) theoretical knowledge GEF code. Examples method presented for main actinides together with...
Simulation of nuclear systems requires complete data that represents the relevant physics. This many types experimental measurements, theoretical physics, semi-empirical models and software systems, as well experts to integrate guide process. discipline is collectively known data, separate programmes within various European countries, USA, Japan, Russia, other OECD Nuclear Energy Agency (NEA) member countries have been operating for decades. The NEA Working Party on International Data...
The OECD Nuclear Energy Agency (NEA) Science Committee (NSC) established the Expert Group on Multi-physics Experimental Data, Benchmarks and Validation (EGMPEBV) in 2014 to bridge gap between advanced, multi-physics simulation capabilities relatively low availability of dedicated, high-fidelity experimental data benchmarks specifically for modelling tools. EGMPEBV was mandated establish mechanisms certification benchmark models processes procedures validation oversees three task forces,...
Modeling of nuclide densities as a function time within magnetic confinement fusion devices such the JET, ITER, and proposed DEMO tokamaks is performed using Monte Carlo transport codes coupled with Bateman equation solver. The generation reaction rates occurs through either pointwise interpolation energy-dependent tracked particle data nuclear or multigroup (MG) convolution binned fluxes cross sections. MG approach benefits from decreased computational expense portability, but introduces...
Multiple description codes are data compression algorithms designed with the goal of minimizing distortion caused by loss in packet-based or diversity communications systems. Recently, techniques that achieve multiple coding combining embedded source unequal error protection channel have become popular literature. These allow for reconstruction any subset transmitted packets and progressively better reconstructions as more decoded. The given methods may be applied to description. While...