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These publications can be ordered at http://www.oecd.org/publications
Reduction of Capital Costs of Nuclear Power Plants
Price: FF240, US$38, DM72, £24, ¥4 400
A French translation of this publication is also available:
Réduction des coûts en capital des centrales nucléaires
Prix : FF240, US$38, DM72, £24, ¥4 400
Monitoring and Data Management Strategies for Nuclear Emergencies
Price: FF160, US$26, DM48, £16, ¥2 850
A French translation of this publication is also available:
Statégies de surveillance et de gestion de données dans les urgences nucléaires
Prix : FF160, US$26, DM48, £16, ¥2 850
Free publications (via E-mail: email@example.com)
Prediction of Neutron Embrittlement in the Reactor Pressure Vessel:
VENUS-1 and VENUS-3 Benchmarks
Calculations of Different Transmutation Concepts:
An International Benchmark Exercise
Data Bank (leaflet)
La banque de données (dépliant)
The 1999 Catalogue of NEA Publications is available free of charge and may be obtained by sending an e-mail to firstname.lastname@example.org)
The list of all Nuclear Safety documents produced since 1973 is
now available at www.oecd-nea.org/nsd/docs/indexcsni.html
Two important meetings related to NEA nuclear safety activities
were held at the end of 1999:
The 11th Meeting of the Committee on Regulatory Activities on November 29-30 1999, and the 27th Meeting of the Committee on Safety of Nuclear Istallations (CSNI) on December 1 - 3, 1999.
The main purpose of both meetings was to review the activities
carried out by these Committees in 1999 and to approve the activities
proposed for the year 2000. In total more than 40 reports and technical
opinion papers were produced and a number of workshops were held in
this area in 1999.
One of the most important outcomes of the CSNI meeting was the approval of the CSNI Strategic Plan www.oecd-nea.org/nsd/docs/2000/csni-r2000-3.pdf . The reasons for developing the Plan were to ensure that the work of the CSNI is aligned with the NEA Strategic Plan, and to maximise the efficiency of its work in view of the decreasing R&D budgets in Member countries. The basic objectives to be achieved by the plan are better top-down direction of the programme of work, and maintenance of an effective network of technical experts.
The plan specifies a new CSNI mission and identified the
strategic areas of future activities. In addition, the plan included a
number of organisational recommendations, including CSNI restructuring.
Both Committees approved a number of a workshops and seminars to
be organised in future:
· CSNI Workshop on Instrumentation and Monitoring of
Concrete Structures, Brussels, March 22-23, 2000 (see below)
· CSNI Workshop on Advanced Thermal-hydraulic and
Neutronic Codes, Current and Future Applications, Barcelona, April
· Safety of the Nuclear Fuel Cycle, 29th to 31st May 2000,
Japan, Joint Workshop with CSNI, CNRA, CRPPH, and NSC. See www.oecd-nea.org/nsd/reports/final.pdf
· CSNI Specialist Meeting on Safety Performance
Indicators, Madrid, Spain, October 17-19, 2000
· CSNI Workshop on Errors of Commission in Probabilistic
Safety Assessment, November 2000, United States
· CNRAWorkshop on Investing in Trust: Nuclear Regulators
and the Public, Paris, 29 November-1 December 2000
· CSNI Workshop on Human Reliability Data Base (HRAD),
Spring 2001, Europe
· CSNI Workshop on Precursor Analysis, Spring 2001, Europe
A OECD Workshop on the Instrumentation and Monitoring of Concrete
Structures, sponsored by the Committee on the Safety of Nuclear
Installations (CSNI) of the OECD Nuclear Energy Agency (NEA), will be
held on 22-23 March 2000. The Workshop is hosted by
AVN/Belgatom/Electrabel/Tractebel and will take place at the offices of
NPP concrete structures have been built to provide significant
margins against the effects of accidental events. Instrumentation and
monitoring are the channels to assess their actual state and follow
their time evolution. The objective of the workshop is an assessment of
the capability of current instrumentation and monitoring systems to
describe the actual state of structures and detect ageing problems. The
workshop will focus on experience and detect trends for the future.
The Workshop will have three technical sessions devoted to
presentations of issues related to Instrumentation and Monitoring. They
will be followed by a fourth session devoted to a discussion of the
material presented and to the formulation of workshop conclusions.
Session 1 - State of the Art and Regulatory Considerations: The
objective is to emphasise difficulties encountered, evidence of
robustness, and recommendations for improvement and also to give a
regulatory perspective on Instrumentation and Monitoring of concrete
structure as part of safety assessments.
Session 2 - Detecting Ageing: Instrumentation gives valuable
information regarding the in-service performance of containments as
constructed which can be used to confirm the original design
assumptions and that their performance is as intended. Many
containments have shown some degradation during plant life, either in
the concrete itself or in the steel reinforcement or liner. It is of
primary importance that instrumentation should be able to detect ageing
problems and identify performance trends. Also of particular interest
are dynamic instrumentation relevant to ageing and non-nuclear
experience of instrumentation in large and complex structures.
Session 3 - Trends for the Future: This session will focus on
future developments in the Instrumentation and Monitoring field. Can
new technologies ( e.g. optic fibres) help with safety assessment? Can
instrumentation on real structures be used to validate Finite Element
codes? How best can we use monitoring in conjunction with periodic
Session 4 - Panel Discussion.
Back issues of the Nuclear Law Bulletin (Numbers 1-60), in
English and French, are now available in .pdf format on the NEA Web
site, in English at: www.oecd-nea.org/law/nlb/index.html
and in French at: www.oecd-nea.org/law/nlbfr/index.html.
You may view these files using Adobe Acrobat Reader. Future editions of the Nuclear Law Bulletin/Bulletin de droit nucléaire will be made available on the Web site approximately one year after their publication.
From 24-25 January, 2000 the Fourth Workshop on the
Pressurised Water Reactor
Main Steam Line Break Benchmark (PWR-MSLB-4) was held in Paris.
The benchmark uses plant data from the B&W TMI-1 reactor,
2772 MWt, about 900 MWe power, equipped with two Once Through Steam
Generators (OTSG). The general purpose of the activity is to reach a
common understanding concerning the coupling between thermal-hydraulics
and neutronics, with emphasis on 3-D modeling. The considered benchmark
was proposed and specified by PSU, who have co-operated with GPU and
NRC. The activity has been subdivided into three main phases:
1. analysis of the transient with a thermal-hydraulic system code
coupled to a point neutron kinetics model: the purpose of this step is
to reach an understanding of the problem among the participants with
reference mainly to the modeling of the system, including
interpretation of the supplied/available information;
2. analysis of the core performance only, when a 3-D neutron kinetic model is coupled with the thermal-hydraulic code: the main purpose is to evaluate the hypotheses at the basis of the coupling, e.g. looking at their impact on the results;
3. analysis of the entire system performance with the coupled codes: the purpose is to evaluate the importance of the 3-D neutronics modeling in the considered cases, and to establish realistic and assessed methods (i.e. inclusive of codes, nodalisations and use of codes) suitable for safety, licensing and design analyses.
The results of this study are being published in 4 reports.
A kick-off session was devoted to the new proposed BWR Turbine
Trip benchmark for further validation of coupled 3D core/plant system
codes. This benchmark problem is based on experimental data (Peach
Bottom). A first benchmark workshop dedicated to this benchmark is
scheduled for the 8-9 November 2000.
Workshop on Preserving Reactor Physics Experiments Data, 18-19
May, 2000, KFKI, Budapest,
Contact: Janos Gadó KFKI Budapest - E. Sartori email@example.com
Shielding Aspects of Accelerators, Targets and Irradiation
Facilities, SATIF-5, 17-20 July 2000 OECD/NEA, Paris,
Contact P. Vaz firstname.lastname@example.org
Seminar on Fission Gas Behaviour in Water Reactor Fuels, 26-29
-September 2000, Cadarache, France,
Contact: Maxy Noé, Maxy.Noe@cea.fr
1. Physor 2000, 7-11 May 2000, Pittsburg, Pennsylvania, http://www.ans.org/store/i_700281
2. International Conference on "Supercomputing in Nuclear
Applications SNA'2000" , 4-7 September 2000, Tokyo, Japan, JAERI http://wwwndc.jaea.go.jp/Mtgs/2000/index00.html
3. International Conference "Monte Carlo 2000"- Advanced Monte
Carlo for Radiation Physics, Particle Transport Simulation and
Applications", 23-26 October 2000, IST, the Lisbon School of
New NSC Publications:
Prediction of Neutron Embrittlement in the Reactor Pressure
Vessel: VENUS-1 and VENUS-3 Benchmarks
This is the final report of two international blind intercomparison exercises performed to examine the current computation techniques used in NEA Member countries for calculating fast neutron doses to reactor components. arious methodologies and different nuclear data were applied to predict neutron dose rates in the Belgian two-dimensional VENUS-1 and three-dimensional VENUS-3 configurations for comparison with measured data.
This report provides the detailed results from the two
benchmarks. The exercise revealed that three-dimensional neutron
fluence calculations provide results that are significantly more
accurate than those obtained from two-dimensional calculations.
Performing three-dimensional calculations is technically feasible given
the power of today's computers.
Available at: www.oecd-nea.org/science/docs/pubs/nea2128-venus.pdf
Calculations of Different Transmutation Concepts: An
International Benchmark Exercise
The final report of the benchmark on different transmutation concepts has now been published. The benchmark investigates the physics of complex fuel cycles involving reprocessing of spent PWR reactor fuel and its subsequent re-use in different reactor types based on PWRs, fast reactors and an accelerator-driven system (ADS). This report gives the analysis of results of the 15 solutions provided (six for the PWRs, six for the fast reactor and 3 for the accelerator case).
As a follow-up to this benchmark, a further ADS benchmark is
being undertaken to resolve discrepancies identified in the present
benchmark (e.g., considerable differences in calculated initial k-eff
and burn-up reactivity swings). This benchmark can be extended later on
for more complex investigations such as beam trip transient behavior of
Available at: www.oecd-nea.org/science/docs/2000/nsc-doc2000-6.pdf
These reports are available free of charge.
The following courses are scheduled for 2000:
1. MCNP and Visual Editor Training Course, 14-17 March 2000,
Pellissippi State Technical Community College near Knoxville,
Tennessee, Contact: Randy Schwarz, MS K8-34, P. O. Box 999, Richland,
WA 99352 (509-372-4042, fax: 509-372-6421, e-mail: email@example.com
2. Advance Training Course on MCNP-4C, 10-14 April 2000, Imperial College, London, UK, Contact: Enrico Sartori firstname.lastname@example.org
3. Training Course on Nuclear Criticality Safety Using KENO-VI - Handling, Transportation and Storag Spent Fuel -(includes KENO-3D), 15-19 May 2000, Issy les Moulineaux, France, Contact: Steven Bowman & E. Sartori email@example.com
4. "MCNP Introductory Training Course," 3-7 July 2000, University of Stuttgart, Germany, Contact: Enrico Sartori, firstname.lastname@example.org
5. MCNP and Visual Editor Training Course, 9-12 October 2000, Richland, Washington. Contact: Randy Schwarz, MS K8-34, P. O. Box 999, Richland, WA 99352 (509-372-4042, fax: 509-372-6421, e-mail: email@example.com url: http://www.pnl.gov/eshs/software/ved.html)
New software packages available from the Data Bank:
A page giving the list of all new programs in the last 12 months can be found at www.oecd-nea.org/dbprog/cpsnew.html .13-MAR-2000 IAEA1214 TRIGAP,TRIGA REACTOR FLUX,POWER,BURNUP CALC (Arrived) 10-MAR-2000 CCC-0641 NESTLE,FEW-GRP N DIFFN FOR STEADY-STATE & TRANSIENT PROB BY NEM (Tested) 09-MAR-2000 NEA-0919 SRIM,STOPPING POWER & RANGE OF IONS IN MATTER (Arrived) 07-MAR-2000 DLC-0134 ZZ RADDECAY,DECAY DATA_LIB FOR RADIOLOGICAL ASSESSMENT (Tested) 28-FEB-2000 ESTS0154 KIVA3,TRANSIENT MULTICOMPONENT 2- & 3-D REACTIVE FLOWS WITH FUEL SPRAYS (Arrived) 24-FEB-2000 NEA-1210 ZZ HATCHES,DATA LIB FOR RADIO_CHEM MODELLING (Arrived) 16-FEB-2000 PSR-0330 STARCODES,STOPPING_POWER & RANGES FOR ELECTRONS,PROTONS,HE (Tested) 09-FEB-2000 NEA-1622 IFPE/OSIRIS,4 PWR RODS IRRADIATED IN THE CEA OSIRIS REACTOR (Arrived) 07-FEB-2000 NEA-1596 IFPE/AECL-BUNDLE,FISSION GAS RELEASE AND BURNUP ANALYSIS,PHWR FUEL (Arrived) 04-FEB-2000 NEA-1553 SINBAD-FUSION NEUTRONICS BENCHMARK EXPERIMENTS (Tested) 01-FEB-2000 NEA-1615 IFPE/CEA-DEFECT FUEL, EXPERIMENTS IRRADIATED AT CEA GRENOBLE (Arrived) 01-FEB-2000 NEA-1620 RODBURN, A SIMPLE NEUTRONICS CODE FOR FUEL ANALYSIS (Arrived)
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