Fusion Engineering and Design 88 (2013) 2589–2593 Contents lists available at ScienceDirect Fusion Engineering and Design journal h om epa ge: www.elsevier.com/locat e/fusengdes Re-evaluation of the irradiation conditions in the IFMIF test cell based on the EVEDA phase design Keitaro Kondo ∗ , Frederik Arbeiter, Ulrich Fischer, Dennis Große, Volker Heinzel, Axel Klix, Arkady Serikov, Kuo Tian, Viktoria Weber Karlsruhe Institute of Technology (KIT), Eggenstein-Leopoldshafen, Germany h i g h l i g h t s • Nuclear responses in IFMIF HFTM are reevaluated based on the EVEDA phase design. • Latest nuclear data and the EVEDA beam footprint are utilized. • Averaged DPA rate of 26 dpa/y can be achieved in HFTM with 500 cm 3 volume. • He/DPA value in HFTM is very similar as the value of the DEMO first wall. • Neutron flux gradient in HFTM center rigs is less than 10%/cm. a r t i c l e i n f o Article history: Received 14 September 2012 Received in revised form 3 May 2013 Accepted 13 May 2013 Available online 1 July 2013 Keywords: IFMIF EVEDA High flux test module Monte Carlo Neutronics a b s t r a c t A re-evaluation of irradiation conditions in IFMIF utilizing the new EVEDA geometry model has been carried out. The focus is on the re-assessment of the nuclear responses in the High Flux Test Module (HFTM) as well as other Test Modules. The aim of the present analysis is to provide a reliable and realistic estimate based on the latest design and knowledge. To this end, we have utilized state-of-the-art nuclear data and an updated beam footprint as prepared on the basis of deuteron beam dynamics simulations combined with the Monte Carlo code McDeLicious, an enhancement to MCNP5 developed ad hoc for IFMIF neutronics calculations. The present analysis proves that (1) the averaged DPA rate of 26 dpa/y can be achieved in HFTM with 500 cm 3 volume, (2) the He/DPA value for HFTM center rigs is similar as the value expected for DEMO first wall, (3) the neutron flux gradient in HFTM center rigs is less than 10%/cm. © 2013 Karlsruhe Institute of Technology (KIT). Published by Elsevier B.V. All rights reserved. 1. Introduction The International Fusion Materials Irradiation Facility (IFMIF) is devoted to provide an irradiation field for testing fusion reac- tor candidate materials. The project is currently in the so-called EVEDA (Engineering Validation and Engineering Design Activities) phase which aims at producing a detailed engineering design of the facility under the BA (Broader Approach) framework [1]. There are several important users’ requirements for IFMIF in order to properly represent the irradiation conditions expected in a future DEMO reactor. The detailed engineering design and optimization of the facility requires a reliable assessment of such fundamen- tal irradiation properties, e.g., displacements per atom (DPA) distributions, neutron flux gradients and gas production rates. Pre- vious IFMIF neutronic calculations have been conducted with a ∗ Corresponding author. Tel.: +49 721 608 23761; fax: +49 721 608 23718. E-mail address: keitaro.kondo@kit.edu (K. Kondo). manually devised neutronic model with a simple modeling or based on the pre-EVEDA facility design as documented in the IFMIF Com- prehensive Design Report (CDR) of 2003 [2–4]. In the frame of the EVEDA activities, however, the facility design has been significantly revised and, in addition, elaborated with regard to a new engineer- ing lay-out of the Test Cell (TC). As part of these activities, a very detailed 3-dimesional Monte Carlo geometry model of the TC and Test Modules (TMs) was prepared [5]. The present paper is dedicated to a re-evaluation of the irradia- tion conditions in IFMIF utilizing the new EVEDA geometry model described above. The focus is on the re-assessment of the nuclear responses in the High Flux Test Module (HFTM) [6] as well as other TMs. The aim of the present analysis is to provide a reliable and real- istic estimate based on the latest design and knowledge. To this end, we have utilized state-of-the-art nuclear data, an updated beam footprint prepared by beam dynamics simulations, and the Monte Carlo code McDeLicious developed ad-hoc for IFMIF neutronics cal- culations [7]. The condition of the calculation and obtained results are discussed in the present paper. 0920-3796/$ – see front matter © 2013 Karlsruhe Institute of Technology (KIT). Published by Elsevier B.V. All rights reserved. http://dx.doi.org/10.1016/j.fusengdes.2013.05.029