Neutronic analysis for the IFMIF EVEDA reference test cell and test facility

We have established a conceptual design of Advanced Fusion Neutron Source (A-FNS). In order to obtain irradiation data required in qualifying materials of fusion DEMO DT reactor, we newly designed nine test modules (TMs) to be implemented in the A-FNS. The design of the test modules is based on a new distinctive maintenance scheme: ‘horizontal maintenance method integrated with the shielding plug’. By integrating the TMs with the shield plug and transferring those from the test cell to the access cell, we can avoid disconnecting and connecting the huge amounts of the pipes and cables by means of the remote handling inside the test cell. We determined a configuration of the TMs in the test cell so as to achieve the required irradiation data for each of the test modules. The maximum dpa of F82H specimens in the TM for blanket structural material was about 10 dpa/fpy, which was designed to fulfil critical requirement by accumulated irradiation for two years and operation duration for four years with the operation availability of 50%. A-FNS was designed so that the huge amounts of neutrons generated can be utilized for various non-fusion purposes as well as the fusion materials irradiation. We newly designed a module to produce the significant amount of 99Mo for a medical purpose. The module for such a non-fusion purpose can be installed in the test cell with the compatibility of the fusion materials irradiation tests.

Section: Introductionmentioning

confidence: 95%

Section: Multipurpose Usagementioning

confidence: 99%

Conceptual design of advanced fusion neutron source (A-FNS) and irradiation test modules

Sato¹,

Kasugai²,

Ochiai³

et al. 2021

“…The MCNP geometrical model of the IFMIF-DONES test cell was based on the model mdl69, reference MCNP model of the IFMIF Test Cell [40], but removing all the irradiation modules (Medium Flux Test Module and Low Flux Test Module) except the HFTM. In figure 9, horizontal sections of both MCNP geometries are shown: being figure 9(a) the horizontal section of the complete mdl69 geometrical model and figure 9(b) the mdl69 geometrical model adapted to the IFMIF-DONES Test Cell concept.…”

Section: Ifmif-dones Neutron Transport Calculationsmentioning

confidence: 99%

Potential irradiation of Cu alloys and tungsten samples in DONES

Mota¹,

Palermo²,

Laces³

et al. 2017

“…The MCNP model of the DONES test cell used was the last version of IFMIF, the model mdl69 [20], but using the HFTM as a unique irradiation module placed directly behind the back plate and the lithium jet. Figure 1 shows the horizontal cross section, in the center of the irradiation area, of the MCNP geometrical model for both the IFMIF test cell and the DONES test cell.…”

Section: Mcnp Geometrical Modelmentioning

confidence: 99%

Sensitivity of IFMIF-DONES irradiation characteristics to different design parameters

Mota¹,

Ibarra²,

García³

et al. 2015

The DONES (DEMO oriented neutron source) has been conceived as a simplified IFMIF-like plant to provide earlier availability, on a reduced time scale and with a reduced budget-both compared to IFMIF-of basic information on materials damage. The conceptual design of the DONES will consist of a number of changes oriented to reduce the time required for construction and the time required to produce the required damage.This paper evaluates how changes in beam irradiation parameters or geometric issues will affect the damage produced in the specimens located in the experimental irradiation area (test cell) of the DONES. Neutron transport calculations have been performed to evaluate the sensitivity of material radiation effects to different irradiation environments. The neutron transport calculations have been performed using McDeLicious 2011 (based on MCNP5-v1.6), code developed by the KIT research institute to reproduce the IFMIF deuteron-lithium neutron source.With this aim in mind, the materials radiation effects evaluated to analyse the sensitivity to the changes in the irradiation conditions have been the damage dose rate, the He and H production, and the He and H production to damage dose ratio. With the analysis of these parameters it is possible to make an evaluation of the level of primary damage suffered by the specimen placed in the high flux test module (HFTM).Based on results obtained in this paper and taking into account engineering considerations, substantial progress should be possible regarding the optimum design parameters for the irradiation area of the IFMIF-DONES facility.