Nuclear Science and Data Bank Publications


Alphabetical list of titles
Actinide and Fission Product Partitioning and Transmutation (2012)
Eleventh Information Exchange Meeting, San Francisco, California, USA, 1-4 November 2010
Actinide and Fission Product Partitioning and Transmutation + CD-ROM (2010)
Tenth Information Exchange Meeting, Mito, Japan, 6-10 October 2008
Boiling Water Reactor Turbine Trip (TT) Benchmark - Vol. IV (2010)
Volume IV: Summary Results of Exercise 3
Burn-up Credit Criticality Safety Benchmark – Phase VII (2012)
UO2 Fuel: Study of Spent Fuel Compositions for Long-term Disposal
Chemical Thermodynamics of Tin (2012)
Chemical Thermodynamics Volume 12
Independent Evaluation of the MYRRHA Project (2009)
Report by an International Team of Experts
International Evaluation Co-operation (Vol. 33) (2013)
Methods and Issues for the Combined Use of Integral Experiments and Covariance Data (Volume 33)
International Nuclear Data Evaluation Co-operation - CD-ROM (2010)
Complete Collection of Published Reports as of January 2010
JANIS 3 (2010)
A Java-based Nuclear Data Display Program
JEFF 3.1.2 (2012)
Joint Evaluated Nuclear Data Library for Fission and Fusion Applications February 2012
JEFF Reports CD-ROM (2010)
Complete Collection of JEFF Reports 1-22
Janis 3.4 (2012)
A Java-based Nuclear Data Display Program
Minor Actinide Burning in Thermal Reactors (2013)
A Report by the Working Party on Scientific Issues of Reactor Systems
NUPEC BWR Full-size Fine-mesh Bundle Test (BFBT) Benchmark (Vol. II) (2010)
Volume II: Uncertainty and Sensitivity Analyses of Void Distribution and Critical Power - Specification
Nuclear Production of Hydrogen (2010)
Fourth Information Exchange Meeting, Oakbrook, Illinois, United States, 13-16 April 2009
Shielding Aspects of Accelerators, Targets and Irradiation Facilities -- SATIF-11 (2013)
Workshop Proceedings, Tsukuba, Japan, 11-13 September 2012
Shielding Aspects of Accelerators,Targets and Irradiation Facilities - SATIF-10 (2010)
Workshop Proceedings, Geneva, Switzerland, 2-4 June 2010
Structural Materials for Innovative Nuclear Systems (SMINS-2) (2012)
Workshop Proceedings, Daejon, Republic of Korea, 31 August-3 September 2010
Technology and Components of Accelerator-driven Systems (2011)
Workshop Proceedings, Karlsruhe, Germany, 15-17 March 2010
VVER-1000 Coolant Transient Benchmark (2010)
Phase 2 (V1000CT-2) Summary Results of Exercise 1 on Vessel Mixing Simulation

Detailed publication list

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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/.

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Actinide and Fission Product Partitioning and Transmutation
Eleventh Information Exchange Meeting, San Francisco, California, USA, 1-4 November 2010
English, 404 pages, published: 06/01/12
NEA#6996, ISBN: 978-92-64-99174-3
Available online at: http://www.oecd-nea.org/science/reports/2012/nea6996-11thPandT.pdf
In order to provide experts with a forum to present and discuss developments in the field of partitioning and transmutation (P&T), the OECD Nuclear Energy Agency (NEA) has been organising, since 1990, a series of biennial information exchange meetings on actinide and fission product P&T.

These proceedings contain all the technical papers presented at the 11th Information Exchange Meeting, which was held on 1-4 November 2010 in San Francisco, California, USA. The meeting covered national programmes on P&T; fuel cycle strategies and transition scenarios; waste forms and geological disposal; transmutation fuels and targets; pyro and aqueous processes; transmutation physics and materials; and transmutation system design, performance and safety.
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Burn-up Credit Criticality Safety Benchmark – Phase VII
UO2 Fuel: Study of Spent Fuel Compositions for Long-term Disposal
English, 180 pages, published: 02/21/12
NEA#6998, ISBN: 978-92-64-99172-9
Available online at: http://www.oecd-nea.org/science/docs/2012/burn-up-credit-phaseVII.pdf
After spent nuclear fuel (SNF) is discharged from a nuclear reactor, fuel composition and reactivity continue to vary as a function of time due to the decay of unstable nuclides. Accurate predictions of the concentrations of long-lived radionuclides in SNF, which represent a significant potential hazard to human beings and to the environment over a very long period, are particularly necessary for radiological dose assessments.
This report assesses the ability of existing computer codes and associated nuclear data to predict isotopic compositions and their corresponding neutron multiplication factor (keff) values for pressurised-water-reactor (PWR) UO2 fuel at 50 GWd/MTU burn-up in a generic spent fuel cask configuration. Fuel decay compositions and keff values have been calculated for 30 post-irradiation time steps out to one million years.
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Chemical Thermodynamics of Tin
Chemical Thermodynamics Volume 12
English, 644 pages, published: 12/31/12
NEA#6354, ISBN: 978-92-64-99206-1
Available online at: http://www.oecd-nea.org/dbtdb/pubs/tin.pdf
This volume is the 12th in the OECD Nuclear Energy Agency (NEA) "Chemical Thermodynamics" series. It is based on a critical review of the thermodynamic properties of tin, its solid compounds and aqueous complexes, carried out 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 tin, 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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Homogeneous versus Heterogeneous Recycling of Transuranics in Fast Nuclear Reactors
English, 92 pages, published: 12/31/12
NEA#7077, ISBN: 978-92-64-99177-4
Available online at: http://www.oecd-nea.org/science/docs/2012/7077-hvh-recycling-transuranics-fnr.pdf
Fuel transuranics (TRU) multi-recycling is a mandatory feature if both the resource sustainability and the waste minimisation objectives for future fuel cycles are to be pursued. The resulting TRU transmutation can be implemented in fast neutron spectrum reactors according to two main options commonly referred to as the homogeneous and heterogeneous modes.

In this study, the two alternatives have been compared in terms of reactor core feasibility, fuel development and impact on the fuel cycle. The multi-criteria analysis indicates that there are major challenges in minor actinide-loaded fuel development, its experimental validation and possibly in its reprocessing. Both modes of recycling have an impact on the overall fuel cycle, even if at different stages, for example complex target fabrication and handling in the case of heterogeneous recycling and full core fuel fabrication in the case of homogeneous recycling. The study finds that an economic evaluation according to specific implementation scenarios should still be undertaken.
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International Handbook of Evaluated Criticality Safety Benchmark Experiments
September 2011
English, published: 03/26/12
NEA#7038, ISBN: 978-92-64-99163-7
Available online at: http://www.oecd-nea.org/science/wpncs/icsbep/handbook.html
The International Criticality Safety Benchmark Evaluation Project (ICSBEP), originally initiated at the national level by the US Department of Energy in 1992, 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 requirement and placement. Many of the specifications are also useful for nuclear data testing. Example calculations are presented; these calculations do not, however, constitute a validation of the codes or cross-section data.

The evaluated criticality safety benchmark data are presented in nine volumes, containing over 58 000 pages and 533 evaluations with benchmark specifications for 4 552 critical, near-critical or subcritical configurations, 24 criticality alarm placement/shielding configurations with multiple dose points for each, and 200 configurations that have been categorised as fundamental physics measurements that are relevant to criticality safety applications.

New to the handbook are benchmark specifications for the GROTESQUE: Complex Geometric Arrangement of Unreflected HEU (93.15) Metal Pieces experiment (see front cover) that was performed by John T. Mihalczo at the Oak Ridge National Laboratory Critical Experiment Facility in June 1964.
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International Handbook of Evaluated Criticality Safety Benchmark Experiments (DVD)
English, published: 12/31/12
NEA#7080, ISBN: 978-92-64-99192-7
Available online at: http://www.oecd-nea.org/science/wpncs/icsbep/handbook.html
The International Criticality Safety Benchmark Evaluation Project (ICSBEP), originally initiated at the national level by the US Department of Energy in 1992, 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 requirement and placement. Many of the specifications are also useful for nuclear data testing. Example calculations are presented; these calculations do not, however, constitute a validation of the codes or cross-section data.
The evaluated criticality safety benchmark data are presented in nine volumes, containing over 65 000 pages and 549 evaluations with benchmark specifications for over 4 700 critical, near-critical or subcritical configurations, 24 criticality alarm placement/shielding configurations with multiple dose points for each, and 200 configurations that have been categorised as fundamental physics measurements that are relevant to criticality safety applications.
New to the handbook are benchmark specifications for the Water-moderated Square-pitched U(6.90)O2 Fuel Rod Lattices with 0.67 Fuel-to-water Ratio experiments (see front cover) that were performed by a team of experimenters at Sandia National Laboratories between 2009 and 2012.
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International Handbook of Evaluated Reactor Physics Benchmark Experiments (DVD)
English, published: 05/15/12
NEA#7081, ISBN: 978-92-64-99168-2
Available online at: http://www.oecd-nea.org/science/wprs/irphe/irphe-handbook/handbook.html
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 2012 edition of the International Handbook of Evaluated Reactor Physics Benchmark Experiments contains data from 56 experimental series performed at 32 reactor facilities. Fifty-four of the 56 evaluations are published as approved benchmarks; the remaining two are published as draft documents only.

New to the handbook are benchmark specifications for selected configurations from the HTR-PROTEUS Pebble Bed Experimental Program which were performed at the Paul Scherrer Institute’s PROTEUS zero-power research reactor in Villigen, Switzerland between 1992 and 1996.
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JEFF 3.1.2
Joint Evaluated Nuclear Data Library for Fission and Fusion Applications February 2012
English, published: 04/19/12
NEA#7111
Available online at: http://www.oecd-nea.org/dbdata/jeff
The Joint Evaluated Fission and Fusion File is an evaluated library produced through international collaboration among Data Bank member countries co-ordinated by the NEA Data Bank. As of February 2012, JEFF 3.1.2 is the latest update of the general purpose neutron data library.

This DVD contains:
• General purpose incident neutron data in ENDF-6 and ACE formats
• Activation data
• Thermal scattering data
• Incident proton data
• Radioactive decay data
• Neutron-induced fission yields data
• Spontaneous fission yields data
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Janis 3.4
A Java-based Nuclear Data Display Program
English, published: 08/21/12
NEA#7116
Available online at: http://www.oecd-nea.org/tools/abstract/detail/nea-1760/
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Structural Materials for Innovative Nuclear Systems (SMINS-2)
Workshop Proceedings, Daejon, Republic of Korea, 31 August-3 September 2010
English, 444 pages, published: 12/31/12
NEA#6896, ISBN: 978-92-64-99209-2
Available online at: http://www.oecd-nea.org/science/docs/2012/6896-smins-korea-proceedings.pdf
Materials research is a field of growing relevance for innovative nuclear systems, such as Generation IV reactors, critical and sub-critical transmutation systems and fusion devices. For these different systems, structural materials are selected or developed taking into account the specificities of their foreseen operational environment. Since 2007, the OECD Nuclear Energy Agency (NEA) has begun organising a series of workshops on Structural Materials for Innovative Nuclear Systems (SMINS) in order to provide a forum to exchange information on current materials research programmes for different innovative nuclear systems. These proceedings include the papers of the second workshop (SMINS-2) which was held in Daejon, Republic of Korea on 31 August-3 September 2010, and hosted by the Korea Atomic Energy Research Institute (KAERI).

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Potential Benefits and Impacts of Advanced Nuclear Fuel Cycles with Actinide Partitioning and Transmutation
English, 74 pages, published: 09/29/11
NEA#6894, ISBN: 978-92-64-99165-1
Available online at: http://www.oecd-nea.org/science/reports/2011/6894-benefits-impacts-advanced-fuel.pdf
This report provides a comparative analysis of different studies performed to assess the potential impact of partitioning and transmutation (P&T) on different types of geological repositories for radioactive waste in various licensing and regulatory environments. Criteria, metrics and impact measures have been analysed and compared with the goal of providing an objective comparison of the state of the art to help shape decisions on options for future advanced fuel cycles.
P&T allows a reduction of the inventory of the emplaced materials which can have a significant impact on the repository. Such a reduction can also make the uncertainty about repository performance less important both during normal evolution and in the case of disruptive scenarios. While P&T will never replace the need for waste repositories, it has the potential to significantly improve public perception regarding the ability to effectively manage radioactive waste by largely reducing the transuranic (TRU) waste masses to be stored and, consequently, to improve public acceptance of the geological repositories. Both issues are important for the future sustainability of nuclear power.
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Technology and Components of Accelerator-driven Systems
Workshop Proceedings, Karlsruhe, Germany, 15-17 March 2010
English, 442 pages, published: 06/28/11
NEA#6897, ISBN: 978-92-64-11727-3
Available online at: http://www.oecd-nea.org/science/pubs/2011/6897-technology-components.pdf
The accelerator-driven system (ADS) is a potential transmutation system option as part of partitioning and transmutation strategies for radioactive waste in advanced nuclear fuel cycles. These proceedings contain all the technical papers presented at the workshop on Technology and Components of Accelerator-driven Systems held on 15-17 March 2010 in Karlsruhe, Germany. The workshop provided experts with a forum to present and discuss state-of-the-art developments in the field of ADS and neutron sources. It included a special session on the EUROTRANS as well as four technical sessions covering current ADS experiments and test facilities, accelerators, neutron sources and subcritical systems.

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Actinide and Fission Product Partitioning and Transmutation + CD-ROM
Tenth Information Exchange Meeting, Mito, Japan, 6-10 October 2008
English, 454 pages, published: 02/08/10
NEA#6420, ISBN: 978-92-64-99097-5
Available online at: http://www.oecd-nea.org/science/reports/2010/nea6420-actinide10th.html
For the successful deployment of the advanced fuel cycle, it is important to apply partitioning and transmutation (P&T) technologies to radioactive waste management. In order to provide experts with a forum to present and to discuss the latest developments in partitioning and transmutation, the NEA has organised, since 1990, a series of biennial information exchange meetings on actinide and fission product P&T.

These proceedings contain all the technical papers and posters presented at the 10th Information Exchange Meeting, which was held on 6-10 October 2008 in Mito, Japan. The meeting addressed the following technical issues: the impact of P&T on waste management and geological disposal; transmutation fuels and targets; partitioning, waste forms and management; materials, spallation targets and coolants; transmutation physics experiments and nuclear data; and transmutation systems design, performance and safety.
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Boiling Water Reactor Turbine Trip (TT) Benchmark - Vol. IV
Volume IV: Summary Results of Exercise 3
English, 276 pages, published: 10/08/10
NEA#6050, ISBN: 978-92-64-99137-8
Available online at: http://www.oecd-nea.org/science/reports/2010/nea6050-tt-benchmark-vol4.pdf
In the field of coupled neutronics/thermal-hydraulics computation there is a need to enhance scientific knowledge in order to develop advanced modelling techniques for new nuclear technologies and concepts, as well as for current applications.

Recently developed “best-estimate” computer code systems for modelling 3-D coupled neutronics/thermal-hydraulics transients in nuclear cores and for coupling of the core phenomena and system dynamics (PWR, BWR, VVER) need to be compared against each other and validated against results from experiments. International benchmark studies have been set up for that purpose.

The present volume is the last in a series of four and summarises the results of the third benchmark exercise, which analyses a turbine trip (TT) in a BWR in its entirety, involving pressurisation events in which the coupling between core phenomena and system dynamics plays an important role. Exercise 3 also analyses four extreme scenarios which allowed participants to test the capabilities of their code(s) in terms of coupling and feedback modelling. The data made available from experiments carried out at the plant make the present benchmark particularly valuable. The data used are from events at the Peach Bottom 2 reactor (a GE-designed BWR/4).
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International Nuclear Data Evaluation Co-operation - CD-ROM
Complete Collection of Published Reports as of January 2010
English, published: 03/19/10
NEA#6942
Free on request
The NEA International Nuclear Data Evaluation Co-operation programme brings together evaluation projects being carried out in Japan (JENDL), the United States (ENDF), Europe (JEFF) and non-OECD countries (BROND, CENDL and FENDL). The Nuclear Data Section of the International Atomic Energy Agency (IAEA) sponsors the participation of evaluation projects from non-OECD countries.

The Co-operation programme was established to promote the exchange of information on nuclear data evaluations, measurements, nuclear model calculations, validation and related topics, as well as to provide a framework for co-operative activities among the participating projects. The Co-operation programme assesses needs for nuclear data improvements and addresses those needs by initiating joint evaluation and/or measurement efforts. Expert groups are established to solve specific common nuclear data problems. Each expert group produces a final report of its findings.

This CD-ROM contains the full collection of the expert group reports as of January 2010.
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JANIS 3
A Java-based Nuclear Data Display Program
English, published: 07/02/10
NEA#6907
Free on request
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JEFF Reports CD-ROM
Complete Collection of JEFF Reports 1-22
English, published: 03/19/10
NEA#6941
Free on request
The Joint Evaluated File (JEF) project was started in 1982 as a collaborative project among NEA Data Bank member countries. The main objective is to provide participating countries with a common and unique source of nuclear data for the calculation and prediction of different nuclear applications. The first version of the JEF file was issued in 1985, and was followed in spring 1993 by a second version (JEF-2.2). An improved, third version was developed in collaboration with the European Fusion File (EFF) project and released in 2005 as the Joint Evaluated Fission and Fusion file (JEFF-3.1). Further updates of the radioactive decay data and neutron data sub-libraries were successively released in 2007 and 2009 as JEFF-3.1.1.

This CD-ROM contains the complete collection of JEF(F) Reports as of January 2010. Among the various JEF(F) publications, reports and documents, only the JEF(F) reports should be used as an official reference.
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NUPEC BWR Full-size Fine-mesh Bundle Test (BFBT) Benchmark (Vol. II)
Volume II: Uncertainty and Sensitivity Analyses of Void Distribution and Critical Power - Specification
English, 44 pages, published: 07/30/10
NEA#6343, ISBN: 978-92-64-99124-8
Available online at: http://www.oecd-nea.org/science/docs/2010/NUPEC-BWR-VOL2.pdf
The government of Japan and the Japanese Nuclear Power Engineering Corporation (NUPEC) have released high-quality data, based on a series of void measurements using full-size mock-up tests for boiling water reactors (BWRs), with the aim of assisting the scientific community to advance its understanding of the two-phase flow (a system containing both gas and liquid) in BWR fuel bundles.

An international benchmark, based on the NUPEC data, has been defined to encourage advancement in the development of two-phase flow theory, which is of importance, for example, for the evaluation of the safety margins in a reactor. The benchmark specifications are being designed so that it systematically assesses and compares the capability of the numerical models to predict detailed void distributions and critical powers.

This report is the second in a series and describes the specification of the sensitivity and uncertainty analysis exercises undertaken to assess the accuracy of the results obtained when modelling basic thermal-hydraulics in a single channel relative to void fraction and critical power. Further volumes will be published, with a synthesis showing to what extent the most recent models are capable of predicting two-phase flow in BWR fuel bundles.
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National Programmes in Chemical Partitioning
A Status Report
English, 120 pages, published: 03/10/10
NEA#5425, ISBN: 978-92-64-99096-8
Available online at: http://www.oecd-nea.org/science/reports/2010/nea5425-National-Prog.pdf
Many countries have been performing a wide range of research on the partitioning and transmutation (P&T) of minor actinides and fission products. The aim is to provide greater flexibility in terms of radioactive waste management strategies and deploying advanced nuclear fuel cycles. This report describes recent and ongoing national research programmes related to chemical partitioning in the Czech Republic, France, Italy, Japan, Korea, the Russian Federation, Spain, the United Kingdom and the United States. European Commission research programmes are also included.
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Nuclear Production of Hydrogen
Fourth Information Exchange Meeting, Oakbrook, Illinois, United States, 13-16 April 2009
English, 464 pages, published: 06/24/10
NEA#6805, ISBN: 978-92-64-08713-2
Available online at: http://www.oecd-nea.org/science/pubs/2010/6805-production-hydrogen.pdf
Hydrogen has the potential to play an important role as a sustainable and environmentally acceptable energy carrier in the 21st century. This report describes the scientific and technical challenges associated with the production of hydrogen using heat and/or electricity from nuclear power plants, with special emphasis on recent developments in high-temperature electrolysis and the use of different chemical thermodynamic processes. Economics and market analysis as well as safety aspects of the nuclear production of hydrogen are also discussed.
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Shielding Aspects of Accelerators,Targets and Irradiation Facilities - SATIF-10
Workshop Proceedings, Geneva, Switzerland, 2-4 June 2010
English, 444 pages, published: 12/15/10
NEA#6898, ISBN: 978-92-64-03467-9
Available online at: http://www.oecd-nea.org/science/pubs/2010/6898-satif-10.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 cover a wide range of applications including material science and medical applications. In recent years, requirements from new technological and research applications have emerged while the number of accelerator facilities in operation, being commissioned, designed or planned has significantly grown. Their parameters (such as the beam energy, beam currents and intensities, and target composition) 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 on the development of modelling methods used to assess the effectiveness of such shielding as part of safety analyses.
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VVER-1000 Coolant Transient Benchmark
Phase 2 (V1000CT-2) Summary Results of Exercise 1 on Vessel Mixing Simulation
English, 144 pages, published: 10/05/10
NEA#6964, ISBN: 978-92-64-99152-1
Available online at: http://www.oecd-nea.org/science/reports/2010/nea6964-ex-l-vessel-mixing.pdf
Recently developed best-estimate computer code systems for modelling 3-D coupled neutronics/thermal-hydraulics transients in nuclear reactors need to be validated against results from experiments and compared with each other to help understand how the different modelling methods adopted affect the accuracy of the simulation. This benchmark was set up for that purpose.

This report is one of a series covering benchmarks designed to test modelling methods for a range of transient scenarios in a VVER-1000 reactor. In this case, the transient is initiated by isolation of one steam generator causing asymmetric loop heat-up. The benchmark is based on experiments conducted at the Kozloduy nuclear power plant.

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Independent Evaluation of the MYRRHA Project
Report by an International Team of Experts
English, 44 pages, published: 12/16/09
NEA#6881, ISBN: 978-92-64-99114-9
Available online at: http://www.oecd-nea.org/science/reports/2009/nea6881-MYRRHA.pdf
The renewed interest in nuclear energy – to a large extent stimulated by concerns about global climate change, high volatility of fossil fuel prices and security of energy supply – has also revived discussions on advanced reactor concepts with the potential to reduce significantly the long-term radioactivity of nuclear waste. One of these concepts is an accelerator-driven system (ADS) which combines a particle accelerator with a subcritical reactor core. The Belgian research centre SCK•CEN at Mol has launched a project aiming to construct an ADS consisting of a high energy proton, linear accelerator combined with a lead-bismuth-cooled, subcritical reactor. The project is called MYRRHA (Multi-purpose Hybrid Research Reactor for High-tech Applications).

The Belgian government asked the OECD Nuclear Energy Agency (NEA) to organise an international peer review of the MYRRHA project to provide an independent evaluation as part of the decision-making process. This report presents the findings from the review, which was conducted by a team of seven high-level experts from seven countries, assisted by the NEA Secretariat.