IPAC2012 - List of Authors (Cywinski, R.)

Paper

Title

Page

Thorium Energy Futures

29

S. Peggs, W. Horak, T. Roser
BNL, Upton, Long Island, New York, USA
V.B. Ashley, R.F. Ashworth
Jacobs Engineering, Pasadena, USA
R.J. Barlow, R. Cywinski, R. Seviour
University of Huddersfield, Huddersfield, United Kingdom
J.-L. Biarrotte
IPN, Orsay, France
S. Henderson
Fermilab, Batavia, USA
A. Hutton
JLAB, Newport News, Virginia, USA
J. Kelly
Thor Energy, Oslo, Norway
M. Lindroos
ESS, Lund, Sweden
P.M. McIntyre
Texas A&M University, College Station, Texas, USA
A. Norlin
IThEO, Sweden
H.L. Owen
STFC/DL/ASTeC, Daresbury, Warrington, Cheshire, United Kingdom
G.T. Parks
University of Cambridge, Cambridge, United Kingdom

The potential for thorium as an alternative or supplement to uranium in fission power generation has long been recognised, and several reactors, of various types, have already operated using thorium-based fuels. Accelerator Driven Subcritical (ADS) systems have benefits and drawbacks when compared to conventional critical thorium reactors, for both solid and molten salt fuels. None of the four options – liquid or solid, with or without an accelerator – can yet be rated as better or worse than the other three, given today's knowledge. We outline the research that will be necessary to lead to an informed choice.

Slides MOOBA01 [3.887 MB]

THPPR061

Optimisation Studies of Accelerator Driven Fertile to Fissile Conversion Rates in Thorium Fuel Cycle

4112

C. Bungau, R.J. Barlow, R. Cywinski
University of Huddersfield, Huddersfield, United Kingdom

The need for proliferation-resistance, longer fuel cycles, higher burn up and improved waste form characteristics has led to a renewed worldwide interest in thorium-based fuels and fuel cycles. In this paper the GEANT4 Monte Carlo code has been used to simulate the Thorium-Uranium fuel cycle. The accelerator driven fertile to fissile conversion rates have been calculated for various geometries. Several new classes have been added by the authors to the GEANT4 simulation code, an extension which allows the state-of-the-art code to be used for the first time for nuclear reactor criticality calculations.

THPPR076

Optimising Neutron Production From Compact Low Energy Accelerators

4154

N. Ratcliffe, R.J. Barlow, A. Bungau, R. Cywinski
University of Huddersfield, Huddersfield, United Kingdom
T.R. Edgecock
STFC/RAL, Chilton, Didcot, Oxon, United Kingdom

There is currently much development in accelerator based methods to provide flexible and reliable neutron generators, in response to a decline in the availability of nuclear reactors. In this paper the focus is on neutron production via a low energy DC proton accelerator (1-10 MeV) and light target system. GEANT4 simulations are being used to study various aspects of target design, beginning with studies into light targets, such as lithium and beryllium, which are already in use. Initially the aim is to replicate these designs and benchmark these simulations, with other models and experimental results, before investigating how modifications can improve neutron production and tailor experimental geometries to specific applications such as neutron capture therapy and medical isotope production.

Paper	Title	Page
MOOBA01	Thorium Energy Futures	29
	S. Peggs, W. Horak, T. Roser BNL, Upton, Long Island, New York, USA V.B. Ashley, R.F. Ashworth Jacobs Engineering, Pasadena, USA R.J. Barlow, R. Cywinski, R. Seviour University of Huddersfield, Huddersfield, United Kingdom J.-L. Biarrotte IPN, Orsay, France S. Henderson Fermilab, Batavia, USA A. Hutton JLAB, Newport News, Virginia, USA J. Kelly Thor Energy, Oslo, Norway M. Lindroos ESS, Lund, Sweden P.M. McIntyre Texas A&M University, College Station, Texas, USA A. Norlin IThEO, Sweden H.L. Owen STFC/DL/ASTeC, Daresbury, Warrington, Cheshire, United Kingdom G.T. Parks University of Cambridge, Cambridge, United Kingdom
	The potential for thorium as an alternative or supplement to uranium in fission power generation has long been recognised, and several reactors, of various types, have already operated using thorium-based fuels. Accelerator Driven Subcritical (ADS) systems have benefits and drawbacks when compared to conventional critical thorium reactors, for both solid and molten salt fuels. None of the four options – liquid or solid, with or without an accelerator – can yet be rated as better or worse than the other three, given today's knowledge. We outline the research that will be necessary to lead to an informed choice.
	Slides MOOBA01 [3.887 MB]

THPPR061	Optimisation Studies of Accelerator Driven Fertile to Fissile Conversion Rates in Thorium Fuel Cycle	4112
	C. Bungau, R.J. Barlow, R. Cywinski University of Huddersfield, Huddersfield, United Kingdom
	The need for proliferation-resistance, longer fuel cycles, higher burn up and improved waste form characteristics has led to a renewed worldwide interest in thorium-based fuels and fuel cycles. In this paper the GEANT4 Monte Carlo code has been used to simulate the Thorium-Uranium fuel cycle. The accelerator driven fertile to fissile conversion rates have been calculated for various geometries. Several new classes have been added by the authors to the GEANT4 simulation code, an extension which allows the state-of-the-art code to be used for the first time for nuclear reactor criticality calculations.

THPPR076	Optimising Neutron Production From Compact Low Energy Accelerators	4154
	N. Ratcliffe, R.J. Barlow, A. Bungau, R. Cywinski University of Huddersfield, Huddersfield, United Kingdom T.R. Edgecock STFC/RAL, Chilton, Didcot, Oxon, United Kingdom
	There is currently much development in accelerator based methods to provide flexible and reliable neutron generators, in response to a decline in the availability of nuclear reactors. In this paper the focus is on neutron production via a low energy DC proton accelerator (1-10 MeV) and light target system. GEANT4 simulations are being used to study various aspects of target design, beginning with studies into light targets, such as lithium and beryllium, which are already in use. Initially the aim is to replicate these designs and benchmark these simulations, with other models and experimental results, before investigating how modifications can improve neutron production and tailor experimental geometries to specific applications such as neutron capture therapy and medical isotope production.