Published September 2019 | Version v1
Journal article

Progress in the design development of EU DEMO helium-cooled pebble bed primary heat transfer system

  • 1. Dipartimento di Ingegneria, Universitàdi Palermo, Viale delle Scienze, I-90128 Palermo (Italy)
  • 2. Ansaldo Nucleare, Corso Perrone 25, 16100 Genova (Italy)
  • 3. EUROfusion Consortium, PPPT Department, Boltzmannstr. 2, Garching (Germany)
  • 4. CREATE Consortium, Universitàdi Napoli Federico II, Via Claudio 21, 80125 Napoli (Italy)

Description

Highlights: • The progresses of the Primary Heat Transfer System of the HCPB Breeding Blanket for the DEMO reactor are outlined. • The main components of Ex-Vessel PHTS has been sized to be compliant with the new In-Vessel requirements. • Results highlights that the 2017 HCPB BB PHTS has reached improved thermal-hydraulic and safety characteristics. • Further efforts are still needed to reduce PHTS pressure drops and volumes as well as to improve IHXs performance. -- Abstract: In the frame of the activities promoted and encouraged by the EURO-fusion Power Plant Physics and Technology (PPPT) department aimed at developing the EU-DEMO fusion reactor, strong emphasis has been recently posed to the whole Balance of Plant (BoP) which represents the set of systems devoted to convert the plasma generated thermal power into electricity and to deliver it to the grid. Among these systems, a very important role is played by the Breeding Blanket (BB) Primary Heat Transfer System (PHTS) as it is responsible to extract more than 80% of the fusion plasma power. In this framework, University of Palermo, Ansaldo Nucleare and CREATE have focused their work to improve thermal-hydraulic, safety and integration features of the Ex-Vessel PHTS for the Helium-Cooled Pebble Bed (HCPB) BB concept of DEMO. Starting from the outcomes obtained in 2016 that have allowed to highlight some criticalities which needed design changes, the paper describes progress and developments of the 2017 HCPB PHTS as well as the goals which have been achieved. The results of the research activity carried out show, in fact, i) an increase of the thermal-hydraulic performances, since a reduction in both total coolant inventory and total pressure drop has been respectively reached, ii) a potential improvement of the overall safety characteristics of the system. Nevertheless a critical assessment of these key parameters reveals that some issues are still open in terms of design integration and feasibility of the whole DEMO BoP for the helium-cooled blanket option, indicating that additional efforts are required to make this technology more attractive.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2019.04.006

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2019.04.006;
PII
S092037961930540X;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
146
Journal Page Range
p. 2416-2420
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
SOFT-30: 30. Symposium on fusion technology
Acronym
SI
Dates
16-21 Sep 2018
Place
Giardini Naxos, Sicily (Italy)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
54112062
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BLOWOUT PREVENTERS; BREEDING BLANKETS; COOLANTS; CRITICALITY; ELECTRICITY; HEAT TRANSFER; HELIUM; PERFORMANCE; PLASMA; PRESSURE DROP; THERMAL HYDRAULICS; THERMONUCLEAR POWER PLANTS; THERMONUCLEAR REACTORS
Descriptors DEC
DRILLING EQUIPMENT; ELEMENTS; ENERGY TRANSFER; EQUIPMENT; FLUID MECHANICS; FLUIDS; GASES; HYDRAULICS; MECHANICS; NONMETALS; POWER PLANTS; RARE GASES; REACTOR COMPONENTS; THERMAL POWER PLANTS

Optional Information

Copyright
Copyright (c) 2019 The Authors. Published by Elsevier B.V. All rights reserved.