Development of the PACTITER code and its application to safety analyses of ITER Primary Cooling Water System

Pace, L. Di; Dacquait, Frédéric; Schindler, Patricia; Blet, V.; Nguyen, Frédéric; Philibert, Y.; Larat, B.

doi:10.1016/j.fusengdes.2006.11.002

Cited by 25 publications

(12 citation statements)

References 3 publications

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“…The modeling of radiation sources for ITER has followed an evolution as intense as the geometry treatment, with diverse new methods and tools to deal with them, from the decay of activated of components 32‐34 to Activated Corrosion Products 35 . The modeling of the primary radiation source (neutrons from the plasma) is given here most of the attention.…”

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

confidence: 99%

Improved radiation shielding analysis considering vector calculus

et al. 2020

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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.

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

confidence: 99%

Improved radiation shielding analysis considering vector calculus

et al. 2020

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“…In such conditions, the diffusion flux in the flow direction can be neglected compared to the convective transport in the same direction. The governing equations that utilize the boundary-layer approximation include the momentum (12), continuity (13), energy (14) and mass transfer (15) equations, which are written in terms of the velocity components U and V (m/s), temperature T (K), pressure P (Pa) and iron concentration C (kg/m 3 ) in PbLi as follows:…”

Section: Turbulent Hydrodynamic Flowsmentioning

confidence: 99%

“…A few numerical codes, mostly 1D, have been developed in the recent past to simulate transport of corrosion products in big multi-component industrial-type water-cooled and liquid-metalcooled loops [12,13] for cooling fusion and fission reactor systems. A typical example of the 1D codes is the MATLIM code developed at FZKA [7,14], where the mass transfer equation is reduced to the 1D form by integrating the original 3D equations over the cross-sectional area of the duct.…”

Section: Introductionmentioning

confidence: 99%

Numerical study of corrosion of ferritic/martensitic steels in the flowing PbLi with and without a magnetic field

Smolentsev¹,

Saedi²,

Malang³

et al. 2013

Journal of Nuclear Materials

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“…The relationship which allows to determine the average material release rate of the test tubes from the measurement of the activity captured in the resin section is given and explained in [1].…”

Section: Simulation Of the Installation Of A Test Loopmentioning

confidence: 99%

“…Hence, the ACP inventory evaluation is an important task for ITER public and occupational safety. PACTITER code versions [1] and its upgrade, OSCARFusion, are computational tools derived from PACTOLE series of codes which were developed by CEA starting from its experience matured for ACP predictions in PWRs. PACTITER v2.1 and following version v3.3 were used by ENEA since 1995, under agreements with CEA, to assess the ACPs inventory in the various loops of ITER Primary Heat Transfer System (PHTS) for different safety analyses (e.g.…”

Section: Introductionmentioning

confidence: 99%

Feasibility study of validating activation corrosion products calculations in cooling water loops at JET

Pace

Batistoni

Bekris

et al. 2013

2013 IEEE 25th Symposium on Fusion Engineering (SOFE)

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This paper presents the feasibility study for verifying the possibility to host an experiment in JET, during a future D-T campaign to validate calculation tools for predicting formation and migration of Activated Corrosion Products, generated by corrosion of base metals, in cooling loops of fusion experiment devices such as ITER. It has been estimated that Activated Corrosion Products inventory generated in an experimental loop with the test section under the neutron flux in a region close to the JET Vacuum Vessel, with the expected D-T campaign neutron fluence, were sufficient to produce a related measurable level in the ion exchange resin of that loop. A solution envisaged for hosting this loop is using vertical ports at the bottom of JET and its surrounding area. A general sketch of main elements required for constructing such a loop was drawn.The relevance for ITER is linked to its licensing, as the ACP radioactive inventory assessment has a two-fold relevance: 1) evaluating the mobilisable radioactive inventory in case of accidents and 2) assessing an important source of direct decay gamma irradiation to staff operating during routine maintenance. The envisaged loop in JET should include the most important materials in the ITER Primary Heat Transfer System loops (copper alloys and stainless steels).

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Development of the PACTITER code and its application to safety analyses of ITER Primary Cooling Water System

Cited by 25 publications

References 3 publications

Improved radiation shielding analysis considering vector calculus

Improved radiation shielding analysis considering vector calculus

Numerical study of corrosion of ferritic/martensitic steels in the flowing PbLi with and without a magnetic field

Feasibility study of validating activation corrosion products calculations in cooling water loops at JET

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