Task on the evaluation of the plasma response to the ITER ELM stabilization coils in ITER H- mode operational scenarios. Technical Specifications
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1 Task on the evaluation of the plasma response to the ITER ELM stabilization coils in ITER H- mode operational scenarios Technical Specifications Version 1 Date: 28/07/2011 Name Affiliation Author G. Huijsmans POP Reviewers A. Loarte POP Approver D.Campbell POP Page 1 of 10
2 Table of Contents 1 Abstract Background and Objectives Scope of Work Work Description Responsibilities (including customs and other logistics) Deliverables and Time Schedule (proposed or required by ITER) Acceptance Criteria (including rules and criteria) Specific requirements and conditions Work Monitoring Meeting schedule Payment schedule / Cost and delivery time breakdown Quality Assurance (QA) requirement References / Terminology and Acronyms...9 Page 2 of 10
3 1 Abstract This task intends to assess the effect of plasma response on the structure of the edge magnetic field created by ELM control coils for ITER operation reference plasmas and draw consequences on the required level of current in the ELM control coils and their spectrum which are required to meet the empirical edge ergodisation criterion for ELM suppression in ITER. The optimization of the ELM control coil spectrum for maximum edge ergodisation with minimum core plasma perturbation including plasma response will be carried out. The effect of plasma response on the expected particle and power fluxes to plasma facing components during ELM suppressed conditions and for mitigated ELM conditions with the application of ELM control coils will be evaluated. 2 Background and Objectives 2.1 The present specification is for the provision of R&D support to the ITER Organization in the area of ELM control. 2.2 General information on the background and objectives of the Task Agreement is described as follows: Type I ELMs in the ITER baseline scenario are expected to cause energy fluxes to the plasma facing components exceeding the threshold for material damage, leading to a reduction in the lifetime of these components. The application of magnetic field perturbation (RMP) by in-vessel coils is one of the methods foreseen to control ELMs in ITER. This method has been successful in the suppression of ELMs in DIII-D and AUG and in strongly mitigating ELMs in JET. The subject is studied in several tokamaks (DIII-D, AUG, JET, NSTX, MAST, TEXTOR). The design criterion for the ITER RMP coils is based on the ergodisation of the edge magnetic field as evaluated by adding the unperturbed plasma magnetic field to the field from the RMP coils assuming that the RMP field propagates in a vacuum. In the different experiments, varying levels of ELM stabilisation/mitigation have been achieved at relatively similar levels of field ergodisation (as calculated with the vacuum RMP perturbation). It has been now demonstrated experimentally that the criterion derived in the vacuum approximation is not a sufficient condition to suppress ELMs. A more accurate description will need to include the response of the plasma to the external magnetic field perturbation applied by the RMP. This response includes both the screening of the perturbation due to the plasma rotation and also, possibly, amplification when the plasma is close to an MHD stability limit. The resulting level of edge ergodisation including the response of the plasma can thus be strongly modified with respect to the vacuum approximation. As a consequence the inclusion of plasma response will also modify the toroidally asymmetric power and particle fluxes to plasma facing components associated with the application of RMP. The response of the plasma to RMP can also strongly modify the penetration of the perturbation towards the core plasma. This can affect the losses of fast particles Page 3 of 10
4 caused by the RMP perturbation as well as the magnitude of the seed island for neoclassical tearing modes that the perturbation can create. 2.3 The objectives of this task are: a) To perform 3D non-linear MHD simulations of the plasma response (rotation screening, amplification) due to the application of magnetic field perturbations by the ELM control coils taking into account the ITER coil/wall+divertor geometry and plasma scenarios, including plasma poloidal and toroidal flows (when appropriate). To evaluate the currents required in the ELM control coils to produce various levels of edge ergodisation of the plasma edge magnetic field, taking into account the plasma response. b) To quantify the effects of the plasma response on the penetration of the magnetic field perturbation towards the plasma centre for the n=2, 3 and n=4 configurations. c) To evaluate the amplification of the edge magnetic perturbations caused by the RMP as a function of the proximity to MHD stability limits which, for the low n perturbations applied, is expected to be the kink/peeling mode limit. d) To perform an optimisation study of the RMP coil currents to maximise the degree of edge magnetic field ergodisation while minimising the perturbation amplitude at the q = 3/2 and 2 surfaces taking into account plasma response. e) To perform an initial self-consistent evaluation of the effects of the RMP including edge magnetic perturbation screening/amplification on the power and particle fluxes between ELMs and during the ELMs The duration of the Task Agreement will be 18 months from the date of the signature by the last of the contracting parties, with the option of extensions to be agreed and defined by both parties. The ITER Organization explicitly reserves the right to decide whether or not to extend the Task Agreement. 3 Scope of Work The work involved in this task concerns the 3D non-linear MHD modelling of the plasma response to the external magnetic perturbations from the ITER ELM control coils. The studies will be carried out for a range of plasma scenarios including : a) the ITER reference inductive scenario at 15 MA for Q DT =10 operation, b) the hybrid and steady-state scenarios aiming at long pulse Q DT = 5 operation and c) additional plasma scenarios or H-mode phases within the reference Q DT =10 scenario, such as those foreseen in the initial phases of operation (e.g. 7.5 MA q 95 =3 He H-modes) and 10 MA/5.3T H-mode plasmas in DT at which the H-mode could be access/exited in the ramp up/down phases of the 15 MA Q DT =10 reference scenario. The modelling of the screening due to plasma rotation requires an accurate description of the plasma poloidal and toroidal flows, in particular of the plasma flows in the H-mode pedestal. The modelling should be carried out using the ITER plasma geometry and include in a selfconsistent way the ExB flow, electron diamagnetic flow and neoclassical flows and an appropriate description of plasma poloidal and toroidal viscosity. The toroidal flows will be provided as input to the modeling from transport simulations by the ITER Organization. The study will be performed for several configurations of the ELM control coils: for the toroidal Page 4 of 10
5 mode numbers (n=2, 3, 4) and for so-called resonant and non-resonant configurations and as a function of the amplitude of the ELM control coil currents. The resulting 3D stationary plasmas obtained will be analysed with respect to the achieved level of edge magnetic field ergodisation, the screening/penetration of the magnetic perturbation in the edge and core plasmas and the toroidal asymmetries in the power flux to the plasma facing components. The coil currents required to obtain the same degree and extent of edge magnetic field ergodisation as that of the ELM suppression criterion derived from vacuum fields will be quantified, including the self-consistent plasma response. The screening/penetration will be analysed for the scenarios described above with a range of q 95 and as a function of the amplitude of the ELM control coil currents. The amplification of the magnetic perturbation will be evaluated by varying the edge bootstrap current (by changing the pedestal pressure height with constant pedestal width) and approaching the MHD stability limit for kink/peeling modes. The study will be done for at least three the ITER scenarios mentioned above covering a relevant range of q 95. The optimisation study will determine whether the spectrum of currents in the ELM coils, as optimised using the vacuum field description criterion, needs to be modified when the plasma response is taken into account to evaluate edge magnetic field ergodisation. The effect of the RMP edge magnetic field perturbation, including the plasma response effect, on the power fluxes to plasma facing components when the edge plasma is in MHD stable conditions as well as their effect on edge MHD stability and on the non-linear evolution of ELMs and their associated power fluxes to PFCs will be assessed for a selected set of plasma conditions. The results obtained as a result of this task will be used for the optimization of the ELM control by RMPs in ITER. 4 Work Description The work involved in this task is sub-divided into the various areas below. All of them should be performed with the same 3-D MHD plasma modeling code that should be capable to describe the non-linear interaction of the plasma with the RMP fields and model the 3-D MHD plasma equilibria and follow their non-linear MHD behaviour for unstable edge conditions self-consistently with the transport of plasma particles, energy and momentum. For some calculations required in the tasks (i.e. the evaluation of the level of edge magnetic field ergodisation, etc.) additional codes (i.e. field line tracing codes) may be required. 1) Establish stationary ITER equilibria with self-consistent flows (neoclassical, diamagnetic, ExB and toroidal flows, for one case for each scenario). For this purpose the static equilibria for various ITER scenarios, provided by the ITER Organization, will be evolved in time using a non-linear MHD code to quasi steady-state (on the relevant time scale) without RMP fields). The scenarios to be modeled will include: i) 15 MA/5.3T reference Q DT = 10 H-mode plasma. For this case a study of the effect of toroidal plasma flow provided from transport simulations by the ITER organization will be performed. ii) iii) 9 MA/5.3T reference Q DT 5 steady-state plasma with internal transport barrier MA/5.3T plasma hybrid scenario conditions for Q DT 5 with burn duration longer than 1000s. Page 5 of 10
6 iv) 7.5 MA/2.65T H-mode plasma, which is the foreseen scenario for development of ELM control methods in the non-active phase. v) 10MA H-mode plasma with Bt = 3.5T and 5.3T as representative of an intermediate development of the scenarios in ITER in from iv) to i) that will be carried out in the non-active or active phase depending on H-mode access power requirements. Additional scenarios maybe studied, if required, following agreement of the IO Task Officer and the DA Task Officer. The total number of different stationary equilibria to be modeled will not exceed 8. 2) Calculate the plasma response by evolving the stationary equilibria with the ELM coils switched on to a new 3D stationary state, using a 3D non-linear MHD code, for a selected set of the scenario equlibria mentioned in 1). The analysis will be performed for the edge magnetic field perturbations with toroidal mode numbers n=2,3,4 for both resonant and non-resonant configurations as estimated by the currents in the coils in the vacuum approximation. The magnitude of the currents and their spectrum will be based on existing vacuum modeling for the various ITER conditions and/or vacuum modeling for ITER carried out as part of the task. The precise specifications will be agreed between the IO Task Officer and the DA Task Officer and will include a reference resonant case with n=4 for each of the equilibria analyzed in 1) with maximum current in the ELM coils (90 kat). In addition, up to 36 cases will be considered for various scenarios and toroidal perturbation numbers in which the current in the ELM control coils and phases are varied to achieve : a) a similar fraction of edge ergodisation for non-resonant and resonant perturbations in the vacuum approximation and b) for resonant and non-resonant perturbations, various level of current in the ELM control coils will be studied to determine the current level required to meet the degree of edge ergodisation required for ELM suppression (as derived from the vacuum field approximation). The edge magnetic field ergodisation will be characterized either by the field line loss fraction or by calculation of the island overlap at the edge by appropriate codes including plasma response. The resulting power and particle fluxes to plasma facing components will be analysed. 3) The amplification of the ELM coil field perturbation as edge MHD stability limits are approached will be studied by varying the edge currents in the pedestal region through variations of the pedestal plasma pressure at constant pedestal width towards the kink/peeling limit for the n=2, 3 and 4 mode numbers for the plasma conditions described in 1). The influence of the edge field amplification on the required currents in the ELM coils for the achievement of a given level of edge ergodisation will be quantified for up to three plasma scenarios and the effect on plasma particle and power fluxes documented both for conditions which remain MHD stable and for those that lead to the triggering of ELMs. 4) For up to three plasma scenarios and two pedestal plasma conditions per scenario, the ELM coil perturbation spectrum with n=3 and 4 toroidal number will be optimized taking into account plasma response. The optimization criteria will aim at maximizing the level of edge magnetic field ergodisation while minimizing the perturbation to the core plasma at the q =3/2 and 2 surfaces. In this respect, the relative merits of ELM control with perturbation with n=4 versus n=3 toroidal number will be evaluated. 5) An initial study of the influence of the RMP perturbation on the non-linear evolution of ELMs in 3D MHD simulations in the 15MA Q DT =10 ITER scenario will be carried out. The study will focus on the influence of the RMP on the onset and mode structure of the ELMs and on the power deposition profiles (with respect to locking of the ELM to the RMP fields). The Page 6 of 10
7 simulations will include a marginally stable case, a weakly unstable and a strongly unstable case, with and without the RMP applied. The detailed specifications for the conditions to be studied will be agreed between the IO Task Officer and the DA Responsible Officer following the kick-off meeting. Depending on the preliminary results some variation in the specification of detailed calculations may be required during the course of the task. Frequent communications between the Contact Persons are therefore envisaged to discuss and agree on details and priorities of the calculations. 5 Responsibilities (including customs and other logistics) Implementing institutions are responsible for the implementation of the task under this Task Agreement. IO is responsible for inputs for the task. The contractor will provide results according to the scope of the work outlined above and agreed between the corresponding Contact Persons, and will fulfil the implementation plan and conditions of present contract. 6 Deliverables and Time Schedule The deliverables are reports describing input data and approximations used in the studies and the results obtained. Details on deliverables and priorities of the studies will be agreed between the IO Task Officers and the DA Task Officer. Intermediate reports will be delivered at approximately 6, 11 and 15 months from the date of signature of the contract, with the final report delivered 18 months from the date of signature of the contract. Three progress meetings will be organized as required to exchange information and to review the intermediate results of the task. Milestone 1 consists of a visit to the ITER site. The subsequent milestones will include a written report and a meeting with contact persons in the ITER Organization (remote and/or in person as required). Milestones: 1. (Month 1) Project kick-off meeting. ~ 2-3 team members will travel to Cadarache to discuss the project in greater detail with the ITER Organization Task ROs and relevant staff and to obtain detailed information on the geometry of ITER components, plasma scenario data, etc., as required for the modelling to be carried out in the task. 2. (Month 6) First Interim Report: Progress report on n=4 RMP response for the ITER scenarios at maximum coil current. 3. (Month 11) Second Interim Report: Progress report on the current requirements to obtain the given level of ergodisation for n=2,3,4 (resonant and non-resonant) configurations. Progress report on the RMP amplification study. 4. (Month 15) Third Interim Report: Progress report on the RMP optimization study and on the non-linear RMP+ELM simulations 5. (Month 18) Final Report and closing meeting. The final report will incorporate comments from the IO on the earlier reports. Page 7 of 10
8 The deliverables are reports describing the statement of each problem, input data and approximations used in the studies and the results obtained (e.g. formulas, figures and EXCEL tables). Details on deliverables and priorities of the studies will be agreed between the Contact Persons. Starting date: Signing of contract. Completion date: 18 months from the date of signature. 7 Acceptance Criteria (including rules and criteria) The deliverable is considered acceptable and will receive actual credit allocation if it meets the following requirement: The items described in Sections 3 & 4 are completed, along with the guidance, clarifications and modifications agreed between the ITER Organization and the DA. 8 Specific requirements and conditions The official language of the ITER project is English. Therefore all input and output documentation relevant for this Contract shall be in English. The Contractor shall ensure that all the professionals in charge of the Contract have an adequate knowledge of English, to allow easy communication and adequate drafting of technical documentation. This requirement also applies to the Contractor s staff working at the ITER site or participating to meetings with the ITER Organization. Documentation developed shall be retained by the contractor for a minimum of 5 years and then may be discarded at the direction of the IO. The use of computer software to perform a safety basis task activity such as analysis and/or modelling, etc shall be reviewed and approved by the IO prior to its use, it should fulfil IO document on calculation code for safety analysis. The work shall require the presence of the Contractor s personnel at the site of the ITER Organization, Cadarache, St Paul-lez-Durance, France, for short time, for the purpose of meetings and data gathering. For all deliverables submitted in electronic format the Contractor shall ensure that the release of the software used to produce the deliverable shall be the same as that adopted by the ITER Organization. 9 Work Monitoring A list of meetings with ITER for progress monitoring shall be submitted by the contractor. 10 Meeting schedule Contractor shall also propose a list of meetings with ITER for progress monitoring in agreement with schedule proposed. At least the following meetings should be foreseen. Scope of meeting Point of check/deliverable Place of meeting Kick-off meeting Work program ITER site Page 8 of 10
9 Progress meetings Checking progress Submission of the Interim Reports ITER site, Contractor site or video conference Closing contract meeting Contract completion Checking of the Final Report ITER site, Contractor site or video conference 11 Payment schedule / Cost and delivery time breakdown tbd 12 Quality Assurance (QA) requirement Prior to commencement of any work, a Quality Plan must be provided to IO for approval. This is a separate document which comprises: 1) a workplan with proposed time schedule and agreed preliminary dates for progress meetings, 2) a statement of those involved in the activity and their approximate role and contribution in time, 3) a statement of what work will be subcontracted and who will responsible for checking this. 13 References / Terminology and Acronyms In the following table denominations and definitions are given of all the actors, entities and documents referred to in this Specification, together with the acronyms used in this document. Page 9 of 10
10 Denomination Definition Acronym ITER Organization For this Contract the ITER Organization IO- ITER Organization Responsible Officer Contractor Contractor s Team Contractor Responsible ITER Organization Task Responsible Officer Contractor Task Responsible Officer Person appointed by the ITER Organization with responsibility to manage all the technical aspects of this contract Firm or group of firms organized in a legal entity to provide the scope of supply. The Contractor plus all the sub-contractors/consultants working under its responsibility and coordination for the performance of the contract The person appointed (in writing) by the legally authorised representative of the Contractor, empowered to act on behalf of the Contractor for all technical, administrative legal and financial matters relative to the performance of this contract Person delegated by the IO-RO for all technical matters, but limited to one specific task order Equivalent to the IO-TRO in the Contractors team. IO-RO C- C-Team C-R IO-TRO C-TRO Page 10 of 10
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