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WPPT Subgroup on Physics and Safety of Transmutation Systems
Scope
The Physics and Safety Subgroup (PSS) of the NEA Working
Party on Partitioning and Transmutation (WPPT) is one of four Subgroups
tasked with supporting the WPPT study to determine the potential viability
of nuclear waste partitioning and transmutation as part of a waste management
strategy. The other subgroups are focused on accelerator utilisation
and reliability, fuels and materials, and chemical separations. In support
of the full NEA WPPT, the Physics and Safety Subgroup will:
- Organise theoretical and expriment-based benchmarks
on minor actinide burner systems
- Evaluate the beam-trip consequences on accelerator-driven
systems
- Perform sensitivity studies on the main parameters
- Propose a safety approach of new P&T systems
.
Objectives
Under the guidance of the WPPT, the major assignments
of the PSS are: To provide Member Countries with up to date information
and results from studies involving the following aspects:
- Reactor physics
- System performances for transmutation
- Reactivity coefficients and kinetics parameters
- Safety
- Safety approach (line of defence, defence in depth)
- Safety analysis (transient analysis)
- Reliability (consequences of beam-trip)
- Control
- Control options
- Sub-critical levels
To cover applications including:
- Reactor for transmutation of plutonium, minor actinides,
long-lived fission products
- For the long term: ADS systems for transmutation
based on scenario analysis carried out by the Expert Group of the NEA
Nuclear Development Division
Method of Work
Meetings will be held in conjunction with major international
meetings, and/or meetings of the full WPPT. Workshops will be organised
to enhance information exchange. Theoretical and experiment-based benchmarks
will be carried out for computer code comparison and validation. Sensitivity
studies will be carried out. Reports (synthesis, recommendations, state-of-the-art)
will be written.
Meetings
- The first meeting of the subgroup will be held
in Issy-les-Moulineaux,
France, on 22-23 April 2002.
Key
Interfaces
Primary interface is with the Accelerator Utilisation
and Reliability Subgroup, regarding requirements on beam and spallation
target reliability.
List
of Activities
- Calculation of Different Transmutation Concepts:
An International Benchmark Exercise (completed in 2000)
In April 1996, the NEA Nuclear Science Committee
(NSC) Expert Group on Physics Aspects of Different Transmutation Concepts
launched a benchmark exercise to compare different transmutation concepts
based on pressurised water reactors (PWRs), fast reactors, and on
accelerator-driven system. The aim was to investigate the physics
of complex fuel cycles involving reprocessing of spent PWR reactor
fuel and its subsequent reuse in different reactor types. The objective
was also to compare the calculated activities for individual isotopes
as a function of time for different plutonium and minor actinide transmutation
scenarios in different reactor systems. 15 solutions were provided
(six for PWRs, six for the fast reactor and three for the accelerator
case). Various computer codes and nuclear data libraries were applied.
The analysis of the detailed results can be found in the OECD/NEA
report "Calculation of Different Transmutation Concepts: An International
Benchmark Exercise", NEA/NSC/DOC(2000)6,
ISBN 92-64-17638-1 (  894
kb ) .
- Comparison Calculations for an Accelerator-Driven
Minor Actinide Burner (completed in 2001)
Recognising a need for code and data validation
in this area, the NEA Nuclear Science Committee initiated a first
benchmark exercise in 1994. The exercise was based on a transmutation
strategy involving light water reactors, fast reactors and an accelerator-driven
system (ADS). The latter, a sodium-cooled system with a tungsten target
and MA-Pu nitride fuel, was analysed by three participants only. Considerable
differences in calculated initial multiplication factor values and
burn-up reactivity swings indicated a need for refining the benchmark
specification and continuing the exercise with a wider participation.
The present benchmark model is designed to resolve the discrepancies
observed in the previous benchmark exercise and, in general, to check
the performance of reactor codes and nuclear data for accelerator-driven
systems with unconventional fuels. The benchmark was launched in July
1999. Seven institutions participated. The final report of the benchmark
will be issued in early 2002.
- MUSE-experiment based ADS benchmark
This first experiment-based benchmark was
launched in December 2001.
- ADS beam trip transient benchmark (specification
in preparation with the collabration with ANL, USA)
Related Conferences and Meetings
- ANS Conference
"AccApp'01 & ADTTA '01: Nuclear Applications in the New Millennium",
Reno, Nevada, USA, 11-15 November 2001
- International
Conference on the New Frontiers of Nuclear Technology : Reactor Physics,
Safety and High-Performan- ce Computing (PHYSOR
2002), Seoul, Korea, 7-10 October 2002
For more Information
on this Subgroup, please contact Claes Nordborg (Claes.Nordborg@oecd.org
For
more information on activities managed/supported by the NSC, please contact Claes Nordborg ( Claes.Nordborg@oecd.org)
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