Recent results on RFX-mod, the largest Reversed Field Pinch (RFP) experiment, have confirmed a positive increase of the electron and ion temperature vs. plasma current with a trend that allows hypothesizing significant D-T fusion processes in larger devices with higher plasma current. Such an operation, in which the plasma is purely ohmically heated, could give an efficient, robust and cheap fusion neutron source to be used as the basis for a fusion-fission hybrid system. It is worthwhile to remember the advantages of the RFP with respect to Tokamaks and Stellarators: plasma ohmically heated, toroidal winding designed for a magnetic field lower than one-two orders of magnitude with respect to Tokamaks, no divertor, very simple, robust and cheap construction, simple access for remote handling and maintenance. To guarantee an almost continuous neutron production, like required in a hybrid reactor, a solution for a continuously pulsed operation is presented, compatible with a purely magnetic induced plasma current rise and sustainment, without the complication of additional current drive systems. The aim of the paper is to investigate the relationship between the machine size (major and minor plasma radius), the attainable volt-seconds and, consequently, the maximum plasma current and pulse duration. The analysis starts from the experimental RFX-mod data (volt-seconds necessary for plasma current rise, loop voltage during flat top, plasma current rise time) extrapolated towards higher current and plasma size up to values compatibles with a condition of significant neutron production from D-T reactions. The paper will present the results which show a realistic possibility to reach fusion condition in an inductively operated RFP with a proper machine size.

A continuously pulsed Reversed Field Pinch core for an ohmically heated hybrid reactor

Piovan Roberto
2017

Abstract

Recent results on RFX-mod, the largest Reversed Field Pinch (RFP) experiment, have confirmed a positive increase of the electron and ion temperature vs. plasma current with a trend that allows hypothesizing significant D-T fusion processes in larger devices with higher plasma current. Such an operation, in which the plasma is purely ohmically heated, could give an efficient, robust and cheap fusion neutron source to be used as the basis for a fusion-fission hybrid system. It is worthwhile to remember the advantages of the RFP with respect to Tokamaks and Stellarators: plasma ohmically heated, toroidal winding designed for a magnetic field lower than one-two orders of magnitude with respect to Tokamaks, no divertor, very simple, robust and cheap construction, simple access for remote handling and maintenance. To guarantee an almost continuous neutron production, like required in a hybrid reactor, a solution for a continuously pulsed operation is presented, compatible with a purely magnetic induced plasma current rise and sustainment, without the complication of additional current drive systems. The aim of the paper is to investigate the relationship between the machine size (major and minor plasma radius), the attainable volt-seconds and, consequently, the maximum plasma current and pulse duration. The analysis starts from the experimental RFX-mod data (volt-seconds necessary for plasma current rise, loop voltage during flat top, plasma current rise time) extrapolated towards higher current and plasma size up to values compatibles with a condition of significant neutron production from D-T reactions. The paper will present the results which show a realistic possibility to reach fusion condition in an inductively operated RFP with a proper machine size.
2017
Istituto gas ionizzati - IGI - Sede Padova
Inglese
13th International Symposium on Fusion Nuclear Technology
http://www.isfnt-13.org/files/PosterSessionProgram.pdf
September 25-29, 2017
Kyoto, Japan
Reversed Field Pinch
hybrid reactor
volt-second
plasma current
P3-174
1
info:eu-repo/semantics/conferenceObject
none
274
04 Contributo in convegno::04.02 Abstract in Atti di convegno
Piovan Roberto
   Implementation of activities described in the Roadmap to Fusion during Horizon 2020 through a Joint programme of the members of the EUROfusion consortium
   EUROfusion
   H2020
   633053
File in questo prodotto:
Non ci sono file associati a questo prodotto.

I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.

Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.14243/338896
Citazioni
  • ???jsp.display-item.citation.pmc??? ND
  • Scopus ND
  • ???jsp.display-item.citation.isi??? ND
social impact