Nuclear energy generation and waste transmutation using an accelerator-driven intense thermal neutron source

Bowman, C.D.; Arthur, E.D.; Lisowski, P.W.; Lawrence, G.P.; Jensen, Reed J.; Anderson, James L.; Blind, B.; Cappiello, M.W.; Davidson, John; England, T.R.; Engel, L.N.; Haight, R. C.; Hughes, H.G.; Ireland, John R.; Krakowski, R.A.; LaBauve, R.J.; Letellier, Bruce; Perry, R.T.; Russell, Gary J.; Staudhammer, K.P.; Versamis, G.L.; Wilson, W.B.

doi:10.1016/0168-9002(92)90795-6

Cited by 519 publications

(121 citation statements)

References 5 publications

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“…The primary trigger for these new measurements was the need for precise spallation data which were required by various ambitious projects like neutron spallation sources [8,9] and accelerator-driven systems (ADS) for incineration of nuclear waste [10,11,12]. Further applications were also foreseen like the production of radioactive beams [13].…”

Section: Introductionmentioning

confidence: 99%

Nuclide cross-sections of fission fragments in the reaction 208Pb + p at 500 A MeV

et al. 2005

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The isotopic distributions and recoil velocities of the fission fragments produced in the spallation reaction 208 P b + p at 500 A MeV have been measured using the inverse-kinematics technique, a lead beam onto a liquid-hydrogen target, and the high-resolution spectrometer FRS at GSI. The shapes of the different distributions are found in good agreement with previously published data while the deduced total fission cross-section is higher than expected from existing systematics and some previous measurements. From the experimental data, the characteristics of the average fissioning system can be reconstructed in charge, mass and excitation energy, and the average number of post-fission neutrons can be inferred. The results are also compared to different models describing the spallation reaction. The intranuclear cascade code INCL4 followed by the de-excitation code ABLA is shown to describe reasonably well the evolution of the isotopic distribution shapes between 500 and 1000 A MeV.

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Section: Introductionmentioning

confidence: 99%

Nuclide cross-sections of fission fragments in the reaction 208Pb + p at 500 A MeV

et al. 2005

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“…It was initially proposed by Bowman [ 11 that it is still possible to sustain a nuclear fission chain reaction under subcritical conditions, with k slightly below unit, by providing the required balance of neutrons with a steady flow af neutrons from the spallation of an intense beam of protons on a solid target, for instance tungsten, stainless steel or lead. This method has the advantage of a safer operation since the chain reaction, if needed, can be easily controlled by acting on the proton accelerator.…”

Section: -mentioning

confidence: 99%

A superconducting linac as the driver of the energy amplifier

Ruggiero¹

1996

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Because of the safer and more reliable mode of operation, a Superconducting Linac is proposed here as the proton beam accelerator which drives a nuclear plant based on the concept of the Energy Amplifier. The accelerator has also high electric power efficiency. An example based on the net generation of 400 MW (electric) is described here. This requires a proton beam energy of 1 GeV with a continuous beam current of 10 mA, corresponding to a beam power of 10 MW.

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“…In addition to these medical applications, high-energy cross section data are needed for the design of new accelerator-driven technologies to transmute radioactive waste [3], produce spallation neutrons for material science studies, and produce tritium [4]. This paper describes evaluated nuclear cross section data for H, C, N, O, Al, Si, P, Ca, Fe, Cu, W, Hg and Pb, collectively known as the LA150 Library [1], that have been developed in support of the above applications.…”

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confidence: 99%

Neutron, proton, and photonuclear cross-sections for radiation therapy and radiation protection

Chadwick¹

1998

Radiation and Environmental Biophysics

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Les Afamos Natlonsl Moratory, an affirmative astiedequal oppertun"kyempleyer, is operated by the Unheraiiy of CMomia for the U.S. Deparbnent of Ene&y under mntract W-740MNG-36. By accaptanca of this article, the publisher rewgnfzes that the U.S. Gwemment retafns a nonexslustie, reya~free license to pubfii or repreduce the pubfried form of thii scmtributien, or to allow others 10 do SO,for U.S. Government purposes. The k Afamos National Laberatmy requests that the pubfkher identify this article aa wxk perfonnad under the auspicas of the U.S. AbstractWe review recent work at Los Alamos to evaluate neutron, proton, and photonuclear cross sections up to 150 MeV (to 250 MeV for protons), based on experimental data and nucIear model calculations. These data are represented in the ENDF format and can be used in computer codes to simulate radiation transport. They permit calculations of absorbed dose in the body from therapy beams, and through use of kerma coefficients allow absorbed dose to be estimated for a given neutron energy distribution. For radiation protection, these data can be used to determine shielding requirements in accelerator environments, and to calculate neutron, proton,~-ray, and radionuclide production. Illui%rative comparisons of the evaluated cross section and kerma coefficient data with measurements are given.

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Nuclear energy generation and waste transmutation using an accelerator-driven intense thermal neutron source

Cited by 519 publications

References 5 publications

Nuclide cross-sections of fission fragments in the reaction 208Pb + p at 500 A MeV

Nuclide cross-sections of fission fragments in the reaction 208Pb + p at 500 A MeV

A superconducting linac as the driver of the energy amplifier

Neutron, proton, and photonuclear cross-sections for radiation therapy and radiation protection

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