Neutron Sources

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R Senesi - One of the best experts on this subject based on the ideXlab platform.

  • research opportunities with compact accelerator driven Neutron Sources
    Physics Reports, 2016
    Co-Authors: I S Anderson, J M Carpenter, C Andreani, G Festa, G Gorini, C K Loong, R Senesi
    Abstract:

    Abstract Since the discovery of the Neutron in 1932 Neutron beams have been used in a very broad range of applications, As an aging fleet of nuclear reactor Sources is retired the use of compact accelerator-driven Neutron Sources (CANS) is becoming more prevalent. CANS are playing a significant and expanding role in research and development in science and engineering, as well as in education and training. In the realm of multidisciplinary applications, CANS offer opportunities over a wide range of technical utilization, from interrogation of civil structures to medical therapy to cultural heritage study. This paper aims to provide the first comprehensive overview of the history, current status of operation, and ongoing development of CANS worldwide. The basic physics and engineering regarding Neutron production by accelerators, target–moderator systems, and beam line instrumentation are introduced, followed by an extensive discussion of various evolving applications currently exploited at CANS.

J M Carpenter - One of the best experts on this subject based on the ideXlab platform.

  • research opportunities with compact accelerator driven Neutron Sources
    Physics Reports, 2016
    Co-Authors: I S Anderson, J M Carpenter, C Andreani, G Festa, G Gorini, C K Loong, R Senesi
    Abstract:

    Abstract Since the discovery of the Neutron in 1932 Neutron beams have been used in a very broad range of applications, As an aging fleet of nuclear reactor Sources is retired the use of compact accelerator-driven Neutron Sources (CANS) is becoming more prevalent. CANS are playing a significant and expanding role in research and development in science and engineering, as well as in education and training. In the realm of multidisciplinary applications, CANS offer opportunities over a wide range of technical utilization, from interrogation of civil structures to medical therapy to cultural heritage study. This paper aims to provide the first comprehensive overview of the history, current status of operation, and ongoing development of CANS worldwide. The basic physics and engineering regarding Neutron production by accelerators, target–moderator systems, and beam line instrumentation are introduced, followed by an extensive discussion of various evolving applications currently exploited at CANS.

  • gallium cooled target for compact accelerator based Neutron Sources
    Physics Procedia, 2012
    Co-Authors: J M Carpenter
    Abstract:

    Abstract This paper discusses the motivation for gallium cooling of targets of compact accelerator-based Neutron Sources (CANS); summarizes features of the low-power alternative, i.e., water cooling, and the limitations of boiling water heat transfer; lists the properties of liquid gallium; and cites its low hazards potential. I set out working equations for heat transport and fluid flow in liquid gallium and present a concept for a gallium-cooled system, including a scoping calculation of temperatures and pressure drops, and present conclusions and a recommendation.

  • retracted gallium cooled target for compact accelerator based Neutron Sources
    Nuclear Instruments & Methods in Physics Research Section A-accelerators Spectrometers Detectors and Associated Equipment, 2010
    Co-Authors: J M Carpenter
    Abstract:

    Abstract This paper discusses the motivation for gallium cooling of targets of compact accelerator-based Neutron Sources (CANS); summarizes features of the low-power alternative, i.e., water cooling, and the limitations of boiling water heat transfer; lists the properties of liquid gallium; and cites its low hazards potential. I set out working equations for heat transport and fluid flow in liquid gallium and present a concept for a gallium-cooled system, including a scoping calculation of temperatures and pressure drops, and present conclusions and a recommendation.

I S Anderson - One of the best experts on this subject based on the ideXlab platform.

  • research opportunities with compact accelerator driven Neutron Sources
    Physics Reports, 2016
    Co-Authors: I S Anderson, J M Carpenter, C Andreani, G Festa, G Gorini, C K Loong, R Senesi
    Abstract:

    Abstract Since the discovery of the Neutron in 1932 Neutron beams have been used in a very broad range of applications, As an aging fleet of nuclear reactor Sources is retired the use of compact accelerator-driven Neutron Sources (CANS) is becoming more prevalent. CANS are playing a significant and expanding role in research and development in science and engineering, as well as in education and training. In the realm of multidisciplinary applications, CANS offer opportunities over a wide range of technical utilization, from interrogation of civil structures to medical therapy to cultural heritage study. This paper aims to provide the first comprehensive overview of the history, current status of operation, and ongoing development of CANS worldwide. The basic physics and engineering regarding Neutron production by accelerators, target–moderator systems, and beam line instrumentation are introduced, followed by an extensive discussion of various evolving applications currently exploited at CANS.

Weston M. Stacey - One of the best experts on this subject based on the ideXlab platform.

  • tokamak d t fusion Neutron source requirements for closing the nuclear fuel cycle
    Nuclear Fusion, 2007
    Co-Authors: Weston M. Stacey
    Abstract:

    This paper summarizes a series of conceptual design studies conducted with the purpose of determining if tokamak fusion Neutron Sources based on ITER physics and technology could meet the Neutron source requirements for sub-critical fast-spectrum nuclear reactors that would help to close the nuclear fuel cycle by transmuting the transuranics in spent nuclear fuel. The studies were constrained to nuclear reactor and materials technologies under consideration in the US nuclear programme. Fuel cycle studies indicate that fusion Neutron Sources in the range ~200–500 MW would meet the needs of transmutation reactors, depending on other constraints such as materials damage to the nuclear fuel. A tokamak with R = 3.75 m, a = 1.1 m, B = 5.7–5.9 T, q95 = 3.00–4.0, I = 8.3–10 MA, βN = 2.0–2.85, HIPB98 = 1.0–1.06, γcd = 0.6 A Wm−2 would meet these requirements.

  • TRANSMUTATION MISSIONS FOR FUSION Neutron Sources
    Fusion Engineering and Design, 2007
    Co-Authors: Weston M. Stacey
    Abstract:

    Abstract There are a number of potential Neutron transmutation missions (destruction of long-lived radioisotopes in spent nuclear fuel, ‘disposal’ of surplus weapons-grade plutonium, ‘breeding’ of fissile nuclear fuel) that perhaps best can be performed in sub-critical nuclear reactors driven by a Neutron source. The requirements on a tokamak fusion Neutron source for such transmutation missions are significantly less demanding than for commercial electrical power production. A tokamak fusion Neutron source based on the current physics and technology database (ITER design base) would meet the needs of the spent nuclear fuel transmutation mission; the technical issue would be achieving ≥50% availability, which would require advances in component reliability and in steady-state physics operation.

  • capabilities of a dt tokamak fusion Neutron source for driving a spent nuclear fuel transmutation reactor
    Nuclear Fusion, 2001
    Co-Authors: Weston M. Stacey
    Abstract:

    The capabilities of a DT fusion Neutron source for driving a spent nuclear fuel transmutation reactor are characterized by identifying limits on transmutation rates that would be imposed by tokamak physics and engineering limitations on fusion Neutron source performance. The need for spent nuclear fuel transmutation and the need for a Neutron source to drive subcritical fission transmutation reactors are reviewed. The likely parameter ranges for tokamak Neutron Sources that could produce an interesting transmutation rate of 100s to 1000s of kg/FPY (where FPY stands for full power year) are identified (Pfus ≈ 10-100 MW, βN ≈ 2-3, Qp ≈ 2-5, R ≈ 3-5 m, I ≈ 6-10 MA). The electrical and thermal power characteristics of transmutation reactors driven by fusion and accelerator spallation Neutron Sources are compared. The status of fusion development vis-a-vis a Neutron source is reviewed.

S C Wilks - One of the best experts on this subject based on the ideXlab platform.

  • the investigation of high intensity laser driven micro Neutron Sources for fusion materials research at high fluence
    Nuclear Fusion, 2000
    Co-Authors: L J Perkins, B G Logan, M D Rosen, M D Perry, Diaz T De La Rubia, Nasr M Ghoniem, T Ditmire, P T Springer, S C Wilks
    Abstract:

    The application of fast pulse, high intensity lasers to drive low cost DT point Neutron Sources for fusion materials testing at high ux/uence is investigated. At present, high power bench- top lasers with intensities of 10 18 W=cm 2 are routinely employed and systems capable of10 21 W=cm 2 are becoming available. These potentially oer sucient energy density for ecient Neutron production in DT targets with dimensions of around 100 m. Two dierent target concepts are analysed | a hot ion, beam{target system and an exploding pusher target system | and Neutron emission rates are evaluated as a function of laser and target conditions. Compared with conventional beam{target Neutron Sources with steady state liquid cooling, the driver energy here is removed by sacricial vaporization of a small target spot. The resulting small source volumes oer the potential for a low cost, high ux source of 14 MeV Neutrons at close coupled, micro (1 mm) test specimens. In particular, it is shown that a laser driven target with100 J/pulse at 100 Hz (i.e.10 kW average power) and laser irradiances in the range I 2 10 17 10 19 W m 2 =cm 2 could produce primary, uncollided Neutron uxes at the test specimen in the 10 14 10 15 nc m 2 s 2 range. While focusing on the laser{plasma interaction physics and resulting Neutron production, the materials science required to validate computational damage models utilizing 100 dpa irradiation of such specimens is also examined; this may provide a multiscale predictive capability for the behaviour of engineering scale components in fusion reactor applications.