ITER plasma source and building modelling to produce radiation maps

Juárez, R.; Catalán, J.P.; Ogando, F.; López-Revelles, Antonio Jesús; Sauvan, P.; Jakhar, S.; Polunovskiy, E.; Loughlin, M.; Sanz, J.

doi:10.1088/1741-4326/aadf9c

Cited by 20 publications

(11 citation statements)

References 14 publications

(14 reference statements)

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The detailed modelling of the neutron source additionally aides the effort of minimizing the overall uncertainty of JET neutron monitors calibration procedure [3] and is designed for versatile studies and applications in Monte Carlo neutron transport calculations in tokamaks of similar characteristics as JET, e.g. JT-60U [41], KSTAR [42,43], as well as larger future ITER [44] and DEMO tokamaks.…”

Section: Discussionmentioning

confidence: 99%

Multiphysics approach to plasma neutron source modelling at the JET tokamak

et al. 2019

View full text Add to dashboard Cite

A novel multiphysics methodology for the computation of realistic plasma neutron sources has been developed. The method is based on state-of-the-art plasma transport and neutron spectrum calculations, coupled with a Monte Carlo neutron transport code, bridging the gap between plasma physics and neutronics. In the paper two JET neutronics tokamak models are used to demonstrate the application of the developed plasma neutron sources and validate them. Diagnostic data for the record JET D discharge 92436 are used as input for the TRANSP code, modelling neutron emission in two external plasma heating scenarios, namely using only neutral beam injection and a combination of the latter and ion cyclotron resonance heating. Neutron spectra, based on plasma transport results, are computed using the DRESS code. The developed PLANET code package is employed to generate plasma neutron source descriptions and couple them with the MCNP code. The effects of using the developed sources in neutron transport calculations on the response of JET neutron diagnostic systems is studied and compared to the results obtained with a generic plasma neutron source. It is shown that, although there are significant differences in the emissivity profiles, spectra shape and anisotropy between the neutron sources, the integral response of the time-resolved ex-vessel neutron detectors is largely insensitive to source changes, with major relative deviations of up to several percent. However it is calculated that, due to the broadening of neutron spectra as a consequence of external plasma heating, larger differences may occur in activation of materials which have threshold reactions located at DD neutron peak energies. The PLANET plasma neutron source computational methodology is demonstrated to be suitable for detailed neutron source effect studies on JET during DT experiments and can be applied to ITER analyses.

show abstract

Section: Discussionmentioning

confidence: 99%

Multiphysics approach to plasma neutron source modelling at the JET tokamak

et al. 2019

View full text Add to dashboard Cite

show abstract

“…The radiation source considered makes use of the so‐called mosaic‐source approach of SRC‐UNED 36 . A WSSA file computed with D1S‐UNED v3.1.3 38 using an obsolete E‐lite model 30 .…”

Section: Programmable Realization Of the Methodology Principlementioning

confidence: 99%

“…The modeling of the primary radiation source (neutrons from the plasma) is given here most of the attention. A relevant development to address the radiation mapping beyond the bio‐shield was achieved in 2016 (SRC‐UNED 36 ). The ITER Tokamak is one of the most sophisticated machines in the world.…”

Section: Complexity Of the Geometries And Radiation Sources In Simulation Nowadaysmentioning

confidence: 99%

See 1 more Smart Citation

Improved radiation shielding analysis considering vector calculus

et al. 2020

View full text Add to dashboard Cite

Summary The future of nuclear energy in the energy mix faces a permanent scrutiny of safety aspects in conciliation with bridled costs, either fission‐ or fusion‐based. This affects to all the exciting milestones pursued in XXIst. To name few in the field of fission, the deployment of the IVth generation reactors is expected or the definitive solution to the radioactive wastes is sought. A mention apart is made to fusion technology, with ITER as the flagship project. It seeks a virtually infinite energy source, intrinsically safe and with reduced radioactive waste production with respect to fission the first commercial reactor. All these, and many other endeavors, share the operation of sophisticated devices in the presence of intense ionizing radiation fields. Humans and electronics must be protected to ensure safe and reliable performance, while shielding normally represents a large fraction of the budget. This involves nuclear analysis in the design phase to forecast the radiation conditions. The complexity of the simulation of 3D radiation fields that is computationally affordable nowadays is unprecedented. While sophistication in geometries and source definitions has become routine, the resulting complexity of these scalar fields makes their analysis increasingly difficult. The need of enhancement of the analysis techniques is evident today. Vector calculus is proposed following a physical interpretation of the field lines that boosts the analysis capabilities. It identifies the trajectories around which shielding is weakest in an automated errorless and effortless approach. Its power is illustrated with an example relevant to the ITER reactor.

show abstract

“…This is because the nuclear heating and doses due to neutrons and prompt photons may significantly alter the correct functioning of these types of equipment. ITER maintains a radiation maps database with enveloping environment conditions for the general design of equipment [1]. It considers as radiation sources the plasma and the water decay ( 16 N and 17 N).…”

Section: Introductionmentioning

confidence: 99%

Nuclear analysis of the ITER torus cryopumps

et al. 2019

View full text Add to dashboard Cite

The ITER Tokamak will feature six torus cryopumps (TCP) to maintain the vacuum requirements inside the vacuum vessel for plasma operation. They will be connected to the ITER vacuum vessel through the lower ducts, which have limited shielding to ensure an efficient pumping. Therefore, these ducts will represent a relevant path for radiation to travel from the plasma and affect diverse aspects of the ITER facility, such as the electronics allocation or the maintenance operations during the machine shutdown. Previous analyses have addressed these important aspects. Nonetheless, limitations in those studies and design evolution have justified a new analysis, specifically dedicated to the TCP final design review. The results of the nuclear analysis are presented here focusing on the B1 level port cell #4. The TCP design and the associated and neighboring equipment have evolved and updated models have been considered. The TCP modelling has required an explicit heterogeneous treatment of the internal parts. The radiation source from the divertor cooling water pipes running along the port cell ceiling has been considered with the latest available source definition. In terms of methodology, one major improvement has been the modelling of the radiation transmission from C-model to the Tokamak Complex model. Another important improvement has been the consideration of D1SUNED for the determination of shutdown dose rates, covering a broader fraction of the radioactive inventory than in previous studies. The following quantities have been determined: neutron flux, absorbed dose to silicon, 1 MeV equivalent neutron fluence and shutdown dose rates (SDDR) after 10 6 s of cooling time. Finally, a set of proposals have been made to considerably mitigate the SDDR after 10 6 s of cooling. This work represents a realistic and matured source of information of the radiation environment in the ITER TCP port cells as presented in the final design review.

show abstract

ITER plasma source and building modelling to produce radiation maps

Cited by 20 publications

References 14 publications

Multiphysics approach to plasma neutron source modelling at the JET tokamak

Multiphysics approach to plasma neutron source modelling at the JET tokamak

Improved radiation shielding analysis considering vector calculus

Nuclear analysis of the ITER torus cryopumps

Contact Info

Product

Resources

About