Workshop on Advanced Neutron Source and its Application

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Presentation transcript:

Workshop on Advanced Neutron Source and its Application Technical Session 3-1 : High Power Neutron Sources Irradiation-area related issues - introductory slides F. Arbeiter (KIT), A. Ibarra (Ciemat), A. Möslang (KIT), M. Serrano (Ciemat)

Challenges of high power neutron sources for the irradiation area Shielding of the high intensity neutron radiation providing interfaces (cooling, power, signal) through shielding (connectors!) safety of involved alkali metals (if applicable) no moderation of spectrum Exploitation of „directed“ limited extent neutron source gradients of nuclear responses shape of irradiation volume (cuboid vs. cylinders) small irradiation volume  small specimens Handling of high volumetric heating in the specimens limitation of specimen stack size application of heat transfer media Lifetime of involved structural and functional materials lifetime (creep, fatigue) of pressure vessel components lifetime of electrical heaters and instrumentation (n detectors) Priorization of functions / test matrix Irradiation of specimens for PIE In-situ test experiments (creep fatigue, tritium release, ...) general nuclear physics applications, isotopes production etc. F. Arbeiter | IAEA SSTT Consultancy Meeting #1 | Jul 4-6, 2016 | Page 2

Example: Irradiation experiments in the IFMIF Test Cell The HFTM occupies the irradiation space closest to the neutron source ~1015 #n/cm²/s at FW/blanket conditions (LFTM) (MFTM) (HFTM) not planned in IFMIF-DONES Exploded view of TA and TMs F. Arbeiter | Advanced Neutron Source – Irradiation Area related Issues | Nov. 5, 2017 | Page 3

Example: IFMIF HFTM irradiation performance As developed 06/2013 (IFMIF/EVEDA DDD-III for 2x 125mA 40MeV D+ „337 cm³ specimens at > 10dpa/fpy“ (uniaxial horizontal gradients) [Keitaro Kondo, IFMIF/EVEDA HFTM DDD-III, 2013] F. Arbeiter | Advanced Neutron Source – Irradiation Area related Issues | Nov. 5, 2017 | Page 4

HFTM specimen payload (working proposal) 81mm [F. Arbeiter et al., ICFRM-17, 2015] 511°C specimen stack 81 x 40 x 9.3 mm³ 3D temperature map with resolved specimens #/caps. Test type Bounding box [mm] 2x12 Flat tensile (static) 27 x 4.6 x 0.76 2x2 Fracture toughness (Compact Tension) 11.5 x 11.5 x 2.3 Bend bar / Charpy impact 27 x 4 x 3 2x6 Cylindrical fatigue 27 x D4 (gauge 9 x D2) 2x3 Fatigue Crack Growth 11.5 x 11.4 x 4.6 2x8 Pressurized creep tubes 27 x D2.5 t0.25 TEM plates [A. Möslang, Final Report on the EFDA Task TW4-TTMI-003 D4, 2006] F. Arbeiter | Advanced Neutron Source – Irradiation Area related Issues | Nov. 5, 2017 | Page 5

Impact of heating intensities For allowed max. temperature spread, the maximum thickness of the specimen stack inside the capsule depends on the nuclear volumetric heating intensity: Thick capsules allow higher specimen usage fraction vs. „parasitic“ volumes ! [F. Schwab, 2015] ∆𝑇 ∝ 𝑞 ′′′ ⋅ 𝑏 2 𝜆 IFMIF 2x125mA : ~3 W/g IFMIF-DONES 1x125mA : ~1.5 W/g F. Arbeiter | IAEA SSTT Consultancy Meeting #1 | Jul 4-6, 2016 | Page 6

Conclusions The usable volume x dpa product of planned fusion-relevant irr. facilities is limited and neccessitates the use of SSTT A certain spread of nuclear responses (dpa, He/dpa) within the specimen set and even a gradient within individual specimens gage volume have to be accepted and needs to be accommodated in the SSTT data assimilation procedures The spread of temperatures can be limited (on cost of irradiation volume), a few outliers may however occur F. Arbeiter | Advanced Neutron Source – Irradiation Area related Issues | Nov. 5, 2017 | Page 7

Issues to discuss Proper definition of the requirements for the irradiation experiments/facilities now being designed will maximize their use for fusion materials science and FPP licensing ! Priorities for the test matrix materials (RAFM steels, W, Cu, ... base/welded/bonded) test types (tensile, fracture toughness, creep, fatigue, ...) Specimen / testing device for in-situ creep Technologies and methodologies for data evaluation Small Specimen Test Technique (SSTT) data assimilation from „dispersed“ {Tirr, dpa} specimen bases required statistics per test type Promising solutions for technical realizations of the irradiation experiments (heating, cooling, structure, instrumentation) F. Arbeiter | Advanced Neutron Source – Irradiation Area related Issues | Nov. 5, 2017 | Page 8