Nuclear Science and Data Bank Publications


Alphabetical list of titles
International Evaluation Co-operation (Vol. 33) (2013)
Methods and Issues for the Combined Use of Integral Experiments and Covariance Data (Volume 33)
Minor Actinide Burning in Thermal Reactors (2013)
A Report by the Working Party on Scientific Issues of Reactor Systems
Shielding Aspects of Accelerators, Targets and Irradiation Facilities -- SATIF-11 (2013)
Workshop Proceedings, Tsukuba, Japan, 11-13 September 2012

Detailed publication list

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International Handbook of Evaluated Reactor Physics Benchmark Experiments
English, published: 05/26/15
NEA#7258
Available online at: http://www.oecd-nea.org/science/wprs/irphe/
International Handbook of Evaluated Reactor Physics Benchmark Experiments

The International Reactor Physics Experiment Evaluation (IRPhE) Project was initiated as a pilot activity in 1999 by the Organisation for Economic Co-operation and Development.
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Review of Integral Experiments for Minor Actinide Management
English, 137 pages, published: 02/06/15
NEA#7222
Available online at: http://www.oecd-nea.org/science/pubs/2015/7222-review-minor-actinide-management.pdf
Spent nuclear fuel contains minor actinides (MAs) such as neptunium, americium and curium, which require careful management. This becomes even more important when mixed oxide (MOX) fuel is being used on a large scale since more MAs will accumulate in the spent fuel. One way to manage these MAs is to transmute them in nuclear reactors, including in light water reactors, fast reactors or accelerator-driven subcritical systems. The transmutation of MAs, however, is not straightforward, as the loading of MAs generally affects physics parameters, such as coolant void, Doppler and burn-up reactivity.

This report focuses on nuclear data requirements for minor actinide management, the review of existing integral data and the determination of required experimental work, the identification of bottlenecks and possible solutions, and the recommendation of an action programme for international co-operation.

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International Handbook of Evaluated Criticality Safety Benchmark Experiments
English, published: 12/15/14
NEA#7231
Volume of the series: Data Bank
Available online at: http://www.oecd-nea.org/science/wpncs/icsbep/handbook.html
The Criticality Safety Benchmark Evaluation Project (CSBEP) was initiated in October 1992 by the United States Department of Energy. The project quickly became an international effort as scientists from other interested countries became involved. The International Criticality Safety Benchmark Evaluation Project (ICSBEP) became an official activity of the Organisation for Economic Co-operation and Development (OECD) Nuclear Energy Agency (NEA) in 1995.

This handbook contains criticality safety benchmark specifications that have been derived from experiments performed at various critical facilities around the world. The benchmark specifications are intended for use by criticality safety engineers to validate calculation techniques used to establish minimum subcritical margins for operations with fissile material and to determine criticality alarm requirements and placement. Many of the specifications are also useful for nuclear data testing. Example calculations are presented; however, these calculations do not constitute a validation of the codes or cross-section data.

The evaluated criticality safety benchmark data are given in nine volumes. These volumes span approximately 67?000 pages and contain 561 evaluations with benchmark specifications for 4?839 critical, near-critical or subcritical configurations, 24 criticality alarm placement/shielding configurations with multiple dose points for each and 207?configurations that have been categorised as fundamental physics measurements that are relevant to criticality safety applications.

New to the handbook are benchmark specifications for subcritical measurements of a nickel-reflected, plutonium-metal sphere performed at the National Criticality Experiments Research Center (NCERC) by experimenters at the Los Alamos National Laboratory in 2012. A photograph of this experiment is shown on the front cover.

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Chemical Thermodynamics of Iron, Part I, Volume 13a
English, 1124 pages, published: 12/13/13
NEA#6355
Available online at: http://www.oecd-nea.org/dbtdb/pubs/6355-vol13a-iron.pdf
This volume is the 13th in the OECD Nuclear Energy Agency (NEA) "Chemical Thermodynamics" series. It is the first part of a critical review of the thermodynamic properties of iron, its solid compounds and aqueous complexes, initiated as part of the NEA Thermochemical Database Project Phase III (TDB III). The database system developed at the OECD/NEA Data Bank ensures consistency not only within the recommended data sets of iron, but also among all the data sets published in the series. This volume will be of particular interest to scientists carrying out performance assessments of deep geological disposal sites for radioactive waste.
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International Evaluation Co-operation (Vol. 33)
Methods and Issues for the Combined Use of Integral Experiments and Covariance Data (Volume 33)
English, 178 pages, published: 12/20/13
NEA#7171
Volume of the series: Nuclear Science
Available online at: http://www.oecd-nea.org/science/wpec/volume33/volume33.pdf
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International Handbook of Evaluated Reactor Physics Benchmark Experiments (DVD)
March 2013
English, published: 05/13/13
NEA#7140
Available online at: http://www.oecd-nea.org/science/wprs/irphe/irphe-handbook/
The International Reactor Physics Experiments Evaluation Project (IRPhEP) was launched in 1999 by the Organisation for Economic Co-operation and Development (OECD) Nuclear Energy Agency (NEA) Nuclear Science Committee (NSC). While co-ordination and administration of the IRPhEP is managed at the international level by the NEA, each participating country is responsible for the administration, technical direction and priorities of the project within their respective countries. The information and data included in this handbook are available to NEA member countries, to all contributing countries and to others on a case-by-case basis.
This handbook contains reactor physics benchmark specifications that have been derived from experiments performed at various nuclear facilities around the world. The benchmark specifications are intended for use by reactor designers, safety analysts and nuclear data evaluators to validate calculation techniques and data. Example calculations are presented; they do not, however, constitute validation or endorsement of the codes or cross-section data.
The 2013 edition of the International Handbook of Evaluated Reactor Physics Benchmark Experiments contains data from 130 experimental series performed at 47 reactor facilities. One hundred twenty-six of the 130 evaluations are published as approved benchmarks; the remaining four are published as draft documents only.
New to the handbook are benchmark specifications for selected measurements on the very-high-temperature reactor critical assembly (VHTRC) which were performed at the Japan Atomic Energy Agency (JAEA) Tokai Research Establishment in Japan between 1985 and 1996.
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Minor Actinide Burning in Thermal Reactors
A Report by the Working Party on Scientific Issues of Reactor Systems
English, 82 pages, published: 11/18/13
NEA#6997
Available online at: http://www.oecd-nea.org/science/pubs/2013/6997-minor-actinide.pdf
This publication provides an introduction to minor actinide nuclear properties and discusses some of the arguments in favour of minor actinide recycling, as well as the potential role of thermal reactors in this regard. Various technical issues and challenges are examined from the fuel cycle, operations, fuel designs, core management and safety/dynamics responses to safety and economics. The focus of this report is on the general conclusions of recent research that could be applied to thermal reactors. Further research and development needs are also considered, with summaries of findings and recommendations for the direction of future R&D efforts.
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Shielding Aspects of Accelerators, Targets and Irradiation Facilities -- SATIF-11
Workshop Proceedings, Tsukuba, Japan, 11-13 September 2012
English, 202 pages, published: 10/08/13
NEA#7157
Available online at: http://www.oecd-nea.org/science/pubs/2013/7157-satif-11.pdf
Particle accelerators have evolved over the last decades from simple devices to powerful machines, and are having an increasingly important impact on research, technology and daily life. Today they have a wide range of applications in many areas including material science and medical applications. In recent years, new technological and research applications have helped to define requirements while the number of accelerator facilities in operation, being commissioned, designed or planned has grown significantly. Their parameters, which include the beam energy, currents and intensities, and target composition, can vary widely, giving rise to new radiation shielding aspects and problems.
Particle accelerators must be operated in safe ways to protect operators, the public and the environment. As the design and use of these facilities evolve, so must the analytical methods used in the safety analyses. These workshop proceedings review the state of the art in radiation shielding of accelerator facilities and irradiation targets. They also evaluate progress in the development of modelling methods used to assess the effectiveness of such shielding as part of safety analyses.
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Status Report on Structural Materials for Advanced Nuclear Systems
English, 107 pages, published: 10/21/13
NEA#6409
Available online at: http://www.oecd-nea.org/science/pubs/2013/6409-sr-smans.pdf
Materials performance is critical to the safe and economic operation of any nuclear system. As the international community pursues the development of Generation IV reactor concepts and accelerator-driven transmutation systems, it will be increasingly necessary to develop advanced materials capable of tolerating the more challenging environments of these new systems. The international community supports numerous materials research programmes, with each country determining its individual focus on a case-by-case basis. In many instances, similar alloys of materials systems are being studied in several countries, providing the opportunity for collaborative and cross-cutting research that benefits different systems.

This report is a snapshot of the current materials programmes supporting the development of advanced concepts. The descriptions of the research are grouped by concept, and national programmes are described within each concept. The report provides an overall sense of the importance of materials research worldwide and the opportunities for synergy among the countries represented in this overview.
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Validation of the JEFF-3.1 Nuclear Data Library
JEFF Report 23
English, 76 pages, published: 02/14/13
NEA#7079
Available online at: http://www.oecd-nea.org/dbdata/nds_jefreports/jefreport-23/nea7079-jeff23.pdf
The Joint Evaluated Fission and Fusion (JEFF) Project is a collaborative effort among OECD Nuclear Energy Agency (NEA) Data Bank member countries to develop a reference nuclear data library for use in different energy applications. These data can be used to help improve the safety and economy of existing installations, as well as to design advanced nuclear reactors and their associated fuel cycles, including radioactive waste management. The JEFF-3.1 library contains several different data types, including neutron and proton interaction data, neutron activation data, radioactive decay data, fission yield data and thermal scattering data. This report describes the initial validation of the complete JEFF-3.1 library for thermal reactors, fuel cycle, storage and reprocessing, fusion technology and intermediate energy applications. It will be useful for scientists and engineers in national laboratories, universities and industry who use basic nuclear data, and is particularly suitable for those who work with application libraries based on JEFF-3.1.

The JEF/DOC and EFFDOC working documents cited in the report are available online at www.oecd-nea.org/dbdata/nds_jefreports/jefreport-23/.