Insights into prospective fusion reactor cooling systems from fission reactor cooling circuits

T. L. Martin; A. D. Warren; D. Kumar; A. Siberry; R. Springell; R. Holmes; R. Clark; L. Platts; R. Burrows; Chris Harrington; M. Gorley; E. Surrey; S. Rowthu; P. Grundler; S. Ritter

Insights into prospective fusion reactor cooling systems from fission reactor cooling circuits

T. L. Martin, A. D. Warren, D. Kumar, A. Siberry, R. Springell, R. Holmes, R. Clark, L. Platts, R. Burrows, Chris Harrington, M. Gorley, E. Surrey, S. Rowthu, P. Grundler, S. Ritter

Research output: Contribution to conference › Conference Paper

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Abstract

The next generations of nuclear fusion reactors, including ITER and DEMO, will consider several different cooling systems for heat dissipation, power generation and tritium breeding. This includes the water-cooled lithium-lead blanket (WCLL) design, which bears significant similarities to the water-cooled circuit in a pressurised water fission reactor. Preparatory work has begun to analyse how the water chemistry regimes used in light water reactors (LWRs) might be adapted to a fusion cooling system. Mitigation procedures from LWRs such as hydrogen water chemistry, zinc and noble metal addition may prove useful in controlling the rate of corrosion in a WCLL circuit, a system which is also subject to aggressive radiolysis products of water and high flow velocities. In addition, a fusion cooling system must cope with several unique challenges, including higher neutron energies and fluxes, thermal excursions from plasma instability and strong magnetic fields up to 10T.

Original language	English
Number of pages	10
Publication status	Published - 22 Aug 2019
Event	19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, EnvDeg 2019 - Boston, United States Duration: 18 Aug 2019 → 22 Aug 2019

Conference

Conference	19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, EnvDeg 2019
Country	United States
City	Boston
Period	18/08/19 → 22/08/19

Bibliographical note

provisional acceptance date added, based on the conference date.

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Martin, T. L., Warren, A. D., Kumar, D., Siberry, A., Springell, R., Holmes, R., Clark, R., Platts, L., Burrows, R., Harrington, C., Gorley, M., Surrey, E., Rowthu, S., Grundler, P., & Ritter, S. (2019). Insights into prospective fusion reactor cooling systems from fission reactor cooling circuits. Paper presented at 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, EnvDeg 2019, Boston, United States.

Martin, T. L. ; Warren, A. D. ; Kumar, D. ; Siberry, A. ; Springell, R. ; Holmes, R. ; Clark, R. ; Platts, L. ; Burrows, R. ; Harrington, Chris ; Gorley, M. ; Surrey, E. ; Rowthu, S. ; Grundler, P. ; Ritter, S. / Insights into prospective fusion reactor cooling systems from fission reactor cooling circuits. Paper presented at 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, EnvDeg 2019, Boston, United States.10 p.

@conference{05b3b6c7264f4a3480906812fe293115,

title = "Insights into prospective fusion reactor cooling systems from fission reactor cooling circuits",

abstract = "The next generations of nuclear fusion reactors, including ITER and DEMO, will consider several different cooling systems for heat dissipation, power generation and tritium breeding. This includes the water-cooled lithium-lead blanket (WCLL) design, which bears significant similarities to the water-cooled circuit in a pressurised water fission reactor. Preparatory work has begun to analyse how the water chemistry regimes used in light water reactors (LWRs) might be adapted to a fusion cooling system. Mitigation procedures from LWRs such as hydrogen water chemistry, zinc and noble metal addition may prove useful in controlling the rate of corrosion in a WCLL circuit, a system which is also subject to aggressive radiolysis products of water and high flow velocities. In addition, a fusion cooling system must cope with several unique challenges, including higher neutron energies and fluxes, thermal excursions from plasma instability and strong magnetic fields up to 10T.",

author = "Martin, {T. L.} and Warren, {A. D.} and D. Kumar and A. Siberry and R. Springell and R. Holmes and R. Clark and L. Platts and R. Burrows and Chris Harrington and M. Gorley and E. Surrey and S. Rowthu and P. Grundler and S. Ritter",

note = "provisional acceptance date added, based on the conference date. ; 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, EnvDeg 2019 ; Conference date: 18-08-2019 Through 22-08-2019",

year = "2019",

month = aug,

day = "22",

language = "English",

}

Martin, TL , Warren, AD , Kumar, D , Siberry, A , Springell, R, Holmes, R, Clark, R, Platts, L, Burrows, R, Harrington, C, Gorley, M, Surrey, E, Rowthu, S, Grundler, P & Ritter, S 2019, 'Insights into prospective fusion reactor cooling systems from fission reactor cooling circuits', Paper presented at 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, EnvDeg 2019, Boston, United States, 18/08/19 - 22/08/19.

Insights into prospective fusion reactor cooling systems from fission reactor cooling circuits. / Martin, T. L.; Warren, A. D.; Kumar, D.; Siberry, A.; Springell, R.; Holmes, R.; Clark, R.; Platts, L.; Burrows, R.; Harrington, Chris; Gorley, M.; Surrey, E.; Rowthu, S.; Grundler, P.; Ritter, S.

2019. Paper presented at 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, EnvDeg 2019, Boston, United States.

Research output: Contribution to conference › Conference Paper

TY - CONF

T1 - Insights into prospective fusion reactor cooling systems from fission reactor cooling circuits

AU - Martin, T. L.

AU - Warren, A. D.

AU - Kumar, D.

AU - Siberry, A.

AU - Springell, R.

AU - Holmes, R.

AU - Clark, R.

AU - Platts, L.

AU - Burrows, R.

AU - Harrington, Chris

AU - Gorley, M.

AU - Surrey, E.

AU - Rowthu, S.

AU - Grundler, P.

AU - Ritter, S.

N1 - provisional acceptance date added, based on the conference date.

PY - 2019/8/22

Y1 - 2019/8/22

N2 - The next generations of nuclear fusion reactors, including ITER and DEMO, will consider several different cooling systems for heat dissipation, power generation and tritium breeding. This includes the water-cooled lithium-lead blanket (WCLL) design, which bears significant similarities to the water-cooled circuit in a pressurised water fission reactor. Preparatory work has begun to analyse how the water chemistry regimes used in light water reactors (LWRs) might be adapted to a fusion cooling system. Mitigation procedures from LWRs such as hydrogen water chemistry, zinc and noble metal addition may prove useful in controlling the rate of corrosion in a WCLL circuit, a system which is also subject to aggressive radiolysis products of water and high flow velocities. In addition, a fusion cooling system must cope with several unique challenges, including higher neutron energies and fluxes, thermal excursions from plasma instability and strong magnetic fields up to 10T.

AB - The next generations of nuclear fusion reactors, including ITER and DEMO, will consider several different cooling systems for heat dissipation, power generation and tritium breeding. This includes the water-cooled lithium-lead blanket (WCLL) design, which bears significant similarities to the water-cooled circuit in a pressurised water fission reactor. Preparatory work has begun to analyse how the water chemistry regimes used in light water reactors (LWRs) might be adapted to a fusion cooling system. Mitigation procedures from LWRs such as hydrogen water chemistry, zinc and noble metal addition may prove useful in controlling the rate of corrosion in a WCLL circuit, a system which is also subject to aggressive radiolysis products of water and high flow velocities. In addition, a fusion cooling system must cope with several unique challenges, including higher neutron energies and fluxes, thermal excursions from plasma instability and strong magnetic fields up to 10T.

UR - http://www.scopus.com/inward/record.url?scp=85080058647&partnerID=8YFLogxK

M3 - Conference Paper

T2 - 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, EnvDeg 2019

Y2 - 18 August 2019 through 22 August 2019

ER -