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Nuclear Law Bulletin No. 80
ISSN 0304-341X. 2008 subscription (two issues): €106, US$137,
£72, ¥15 700.
Disponible également en français :
Bulletin de droit
nucléaire n° 80
ISSN 0304-3428. Abonnement 2008 (deux numéros) : €106, US$137, £72,
¥15 700.
Free publications are available at
www.nea.fr/html/pub/webpubs/. Paper copies may be requested by
sending an e-mail to
neapub@nea.fr.
Cultural and Structural Changes in Radioactive Waste Management
Organisations
Lessons Learnt
ISBN 978-92-64-99036-4. 44 pages (275 kb).
Disponible également en français :
Changements culturels et organisationnels dans les organismes de
gestion des déchets radioactifs
ISBN 978-92-64-99037-1. 44 pages (396 ko).
Experience from the Third International Nuclear Emergency Exercise (INEX
3) on Consequence Management
ISBN 978-92-64-99040-1. 48 pages (195 kb).
Disponible également en français :
Enseignements tirés du troisième Exercice international d'urgence
nucléaire (INEX 3) sur la gestion des conséquences
ISBN 978-92-64-99041-8. 48 pages (207 ko).
NEA News
ISSN 1605-9581. 44 pages (2.5 mb).
Disponible également en français :
AEN
Infos
ISSN 1605-959X. 44 pages (1,3 mo).
Regulating the Long-term Safety of Geological Disposal
Towards a Common Understanding of the Main Objectives and Bases of
Safety Criteria
ISBN 978-92-64-99031-9. 82 pages (380 kb).
Strategy for Developing and Conducting Nuclear Emergency Exercises
ISBN 978-92-64-99038-8. 38 pages (305 kb).
Disponible également en français :
Une stratégie pour la conception et la réalisation des exercices d'urgence
nucléaire
ISBN 978-92-64-99039-5. 42 pages (143 ko).
Nuclear safety
A new NEA Working Group on the Regulation of New Reactors (WGRNR)
has been established. The working group will address the regulatory
aspects of the siting, licensing and regulatory oversight of
generation III+ and generation IV nuclear reactors. The WGRNR will
focus on construction inspection issues and share this experience
with the other groups working under the aegis of the NEA Committee
on Nuclear Regulatory Activities (CNRA). The WGRNR will also
co-ordinate its activities with the work performed by the
Multinational Design Evaluation Programme (MDEP) such that any
duplication of effort is avoided. More information is available at
www.nea.fr/html/nsd/cnra/wgrnr.html.
An NEA workshop on the Role of Research in a Regulatory Context was
held on 5 December 2007 at the NEA offices in Issy-les-Moulineaux,
France. In the course of the workshop participants examined the
safety research needs for reactors in service, under construction
and in development. They concluded that the NEA Committee on the
Safety of Nuclear Installations (CSNI) needs to develop a long-term
strategy in this area. The CSNI strategy should identify the key
safety and risk issues associated with particular design concepts,
which of these issues require experimental data, and the
infrastructure required to gather this data.
Nuclear development
Renewed
interest in including nuclear energy in the energy mix of many
member countries raises the question of potential raw material
limits to nuclear energy growth. The NEA has therefore convened an
ad hoc expert group to examine the issue. The expert group, which is
comprised of representatives from NEA member countries, the European
Union and the International Atomic Energy Agency, will consider all
materials required for the construction and operation of nuclear
power plants and their associated fuel cycle facilities. Expert
group members have already carried out a preliminary assessment by
comparing global resource estimates with the requirements arising
from a hypothetical tenfold expansion of nuclear generating capacity.
The expert group is also investigating other sources of data on raw
material inputs, with a particular focus on specialty materials used
in nuclear fuel manufacture. Once a complete list of critical
material requirements is compiled, simulations of the impact on raw
material supplies under more realistic scenarios of nuclear capacity
development will be performed. An assessment of material
requirements for new reactor designs will also be undertaken with
input from nuclear power plant vendors. More information is
available at
www.nea.fr/html/ndd/limits.html.
Nuclear science
The NEA Working Party on Multi-scale Modelling of Fuels and
Structural Materials for Nuclear Systems (WPMM) met for the first
time on 15-16 January 2008 at the NEA offices in Issy-les-Moulineaux,
France. The WPMM will review and evaluate the multi-scale modelling
and simulation techniques currently employed in the selection of
materials used in nuclear systems. During this meeting WPMM members
shared past experience in developing models for assessing nuclear
materials and identified a number of areas of study that they plan
to explore further. More information is available at
www.nea.fr/html/science/wpmm/.
The fourth NEA workshop on the coupled neutronics/thermal-hydraulics
transient benchmark for pebble bed modular reactors was held on
21-25 January 2008 at the NEA offices. Workshop participants were
trained in the use of the new DIREKT computer code (which performs
time-dependent, two-dimensional simulations of thermal-hydraulic
transients in gas-cooled nuclear reactors) and the modelling of the
benchmark. Participants also worked on a series of steady state and
transient problems with solutions provided by several independently
developed computer codes. More information is available at
www.nea.fr/html/science/wprs/pbmr400/.
A new Research and test facilities database (RTFDB) has just been
launched on the NEA website. The database, set up by the NEA Expert
Group on Needs of R&D Facilities in Nuclear Science, was established
as part of the expert group's worldwide reviewer of the status of
research and test facilities in the field of nuclear science and
technology. Information in the database was initially collected from
the internet and other published sources before being verified by
independent reviewers. The database is available at
www.nea.fr/rtfdb/.
Data Bank
Nuclear data services
The following nuclear data libraries have recently been added to the
evaluated nuclear data (EVA) database:
- Proton activation data file (PADF-2007);
- International reactor dosimetry file (IRDF-2002);
- International cross-section standards.
The EVA database contains a large number of evaluated data libraries,
all in ENDF format; it can be consulted at
www.nea.fr/html/dbdata/eva/evaret.cgi.
The PADF-2007 and IRDF-2002 libraries are also available in the
NEA-developed nuclear data display program JANIS. JANIS, now in its
third release, is designed to facilitate the visualisation and
manipulation of nuclear data. Its objective is to allow the nuclear
data user to view numerical values and graphical representations
without necessarily being familiar with the storage format. It
offers maximum flexibility for the comparison of different nuclear
data sets. More information is available at
www.nea.fr/janis/.
Computer program services
The NEA held a course on Analytical Benchmarks: Case Studies in
Neutron Transport Theory on 30 January-1 February 2008 at the NEA
offices in Issy-les-Moulineaux, France. The objective of the course
was to give participants a grounding in the fundamental concepts of
neutron transport theory, including recent theoretical and numerical
advances in analytical benchmarking. Course participants included
neutron transport method developers, teachers of reactor physics and
neutron transport theory as well as several doctoral students. A
list of the NEA courses in this field scheduled for 2008 can be
found at
www.nea.fr//html/dbprog/.
New computer
programs available
Forthcoming workshops and seminars
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16-JAN-2008 |
NEA-1737 |
TALYS-1.0, Computes nuclear reactions cross-sections, yields
and spectra via a comprehensive set of nuclear models
(Arrived) |
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15-JAN-2008 |
NEA-1735 |
CARL
2.3, Radiotoxicity, activity, dose and decay power
calculations for spent fuel
(Arrived) |
|
20-DEC-2007 |
NEA-1798 |
ANGELO-LAMBDA, Covariance matrix interpolation and
mathematical verification
(Now tested) |
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19-DEC-2007 |
NEA-1730 |
ZZ
COV-15GROUP-2006, 15-group cross-section covariance matrix
library
(Now tested) |
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19-DEC-2007 |
USCD1236 |
ZZ-SCALE5.1/COVA-44G, 44-group cross-section covariance
matrix library extracted from SCALE5.1
(Now tested) |
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18-DEC-2007 |
NEA-0914 |
REFIT,
Multi-level Resonance Parameter Least Square Fit of Neutron
Transmission and Capture Data
(Now tested) |
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10-DEC-2007 |
USCD1218 |
STANEF,
ENDF/B Book-keeping Operations for ENDF Format Files
(Now tested) |
|
10-DEC-2007 |
USCD1212 |
INTER,
ENDF/B Thermal Cross-Sections, Resonance Integrals,
G-Factors Calculation
(Now tested) |
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10-DEC-2007 |
USCD1216 |
PSYCHE,
ENDF/B Data Consistency Check in ENDF Format
(Now tested) |
|
10-DEC-2007 |
USCD1209 |
FIZCON,
ENDF/B Cross-Sections Redundancy Check
(Now tested) |
|
10-DEC-2007 |
USCD1208 |
CHECKR,
ENDF/B Format Check
(Now tested) |
|
10-DEC-2007 |
USCD1235 |
ENDF-UTILITY-CODES, Codes to check and standardise data in
the Evaluated Nuclear Data File (ENDF)
(Now tested) |
|
10-DEC-2007 |
IAEA1313 |
MIXER2007, Cross-Section Calculations for a Composite
Mixture of ENDF Format Material
(Now tested) |
|
07-DEC-2007 |
IAEA1309 |
FIXUP2007, ENDF Format Redundant Cross-Section Check
(Now tested) |
|
07-DEC-2007 |
IAEA1322 |
EVALPLOT2007, ENDF Plots Cross-Section, Angular Distribution
and Energy Distribution
(Now tested) |
|
07-DEC-2007 |
IAEA1308 |
DICTIN2007, Reaction Index Generated for ENDF Format
(Now tested) |
|
07-DEC-2007 |
IAEA1307 |
CONVERT2007, FORTRAN Program Converter for Different
Computers
(Now tested) |
|
07-DEC-2007 |
IAEA1321 |
COMPLOT2007, Compare ENDF/B Plots of Reaction Data
(Now tested) |
|
07-DEC-2007 |
IAEA1380 |
ACTIVATE2007, Activation Cross-Section by Combining
Cross-Section and Multiplier (ENDF Fomat)
(Now tested) |
|
07-DEC-2007 |
IAEA1379 |
PREPRO2007, Data Preparation and Management, Subsidiary
Calculations (ENDF Format)
(Now tested) |
|
07-DEC-2007 |
IAEA0932 |
VIRGIN2007, Calculates Uncollided Neutron Flux and Neutron
Reactions from Transmission in ENDF Format
(Now tested) |
|
07-DEC-2007 |
IAEA1283 |
SIXPAK2007, ENDF Format Double Differential Cross-Section
Converter to Single Differential Format
(Now tested) |
|
07-DEC-2007 |
IAEA0854 |
SIGMA1-2007, Doppler Broadening ENDF Format Linear-Linear.
Interpolated Point Cross-Section
(Now tested) |
|
07-DEC-2007 |
IAEA1314 |
RELABEL2007, Labels FORTRAN Statements in ENDF Format
Processing Programs
(Now tested) |
|
07-DEC-2007 |
IAEA0848 |
RECENT2007, Reconstruction of Cross-Section Data from
Resonance Parameters
(Now tested) |
|
07-DEC-2007 |
IAEA1312 |
MERGER2007, Merges ENDF/B Data by Material Number or
Identifier
(Now tested) |
|
07-DEC-2007 |
IAEA1311 |
LINEAR2007, Linear-linear Interpolation of ENDF Format
Cross-Sections
(Now tested) |
|
07-DEC-2007 |
IAEA1310 |
LEGEND2007, Angular Distribution Table Calculations in ENDF
Format
(Now tested) |
|
07-DEC-2007 |
IAEA0849 |
GROUPIE2007, Bondarenko Self-Shielded Cross-Sections from
ENDF/B
(Now tested) |
|
06-DEC-2007 |
CCC-0601 |
GENII-1.485, GENII-LIN, Multi-purpose Health Physics Code
(Now tested) |
|
04-DEC-2007 |
PSR-0533 |
SQUIRT
1.1, Predicts leakage rate and crack area for cracked pipes
in nuclear power plants
(Arrived) |
|
04-DEC-2007 |
PSR-0523 |
DEPLETOR Version 2, Provides depletion capability to the
Purdue Advanced Reactor Core Simulator (PARCS) code
(Arrived) |
|
04-DEC-2007 |
PSR-0482 |
REMIT5.1, Radiation exposure monitoring and information
transmittal system
(Arrived) |
|
04-DEC-2007 |
CCC-0729 |
SERA-1C0, Simulation environment for radiotherapy
applications
(Arrived) |
|
04-DEC-2007 |
ESTS0608 |
RSAC-6, Gamma doses, inhalation and ingestion doses, fission
products inventory after fission products release
(Arrived) |
|
04-DEC-2007 |
ESTS1365 |
NLCGCS_MPV3.0, Inversion of electromagnetic fields for
subsurface electrical properties
(Arrived) |
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