Neutron yields from proton-induced spallation reactions in thick targets of lead

Lone, M.A.; Wong, Philip

doi:10.1016/0168-9002(95)00286-3

Cited by 11 publications

(3 citation statements)

References 10 publications

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“…In other codes, like MCNP for example, the Bertini model is used by default for nucleons and pions, while the ISABEL model is used for other particle types [4]. The Bertini model does not take into account the nuclear structure effects in the inelastic interactions during the intranuclear cascade and therefore the code modelling of interactions at energies much below 100 MeV is questionable [5]. On the other hand, GEANT4 does not offer default models, it is the user's responsibility to select the appropriate model for each specific application.…”

Section: Computation Detailsmentioning

confidence: 99%

Target Studies for the Production of Lithium8 for Neutrino Physics Using a Low Energy Cyclotron

Bungau,

Barlow,

Shaevitz

et al. 2012

Preprint

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Lithium 8 is a short lived beta emitter producing a high energy anti-neutrino, which is very suitable for making several measurements of fundamental quantities. It is proposed to produce Lithium 8 with a commercially available 60 MeV cyclotron using protons or alpha particles on a Beryllium 9 target. We have used the GEANT4 program to model these processes, and calculate the anti-neutrino fluxes that could be obtained in a practical system. We also calculate the production of undesirable contaminants such as Boron 8, and show that these can be reduced to a very low level.

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Section: Computation Detailsmentioning

confidence: 99%

Target Studies for the Production of Lithium8 for Neutrino Physics Using a Low Energy Cyclotron

Bungau,

Barlow,

Shaevitz

et al. 2012

Preprint

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“…Spallation becomes very efficient at higher proton energies above a few hundred MeV and, depending upon the (high-Z) target material and dimensions, a broad optimum exists around 1 GeV incident proton energy where there is an optimal trade-off between the energy expended to accelerate protons and the number of neutrons generated per proton. A 1 GeV proton beam generates typically over 20 neutrons per proton (n/p) from a lead target of sufficient length and radius (Lone and Wong (1995), Hilscher et al (1998)). However, whilst this efficiency is required to generate the copious number of neutrons for a high-power, low k ef f subcritical system, for a lower-power demonstrator it is much more cost-effective to reduce the proton energy.…”

Section: Accelerator Proton Sourcementioning

confidence: 99%

“…Conceptual ADS designs often consider reactor powers of up to 1 GW(e) output, in which a 1 GeV proton beam drives spallation efficiently in a lead target, with ∼20 neutrons per proton (n/p) being a typical production ratio (Lone and Wong (1995)). Safety considerations mean that subcritical k ef f values between 0.95 and 0.98 are typically considered (Nifenecker et al (1999)), which combined with the reactor output implies beam powers in ex-cess of 5 MW.…”

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confidence: 99%

Steady-state neutronic analysis of converting the UK CONSORT reactor for ADS experiments

Owen¹,

Gill²,

Chambers³

2011

Annals of Nuclear Energy

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CONSORT is the UK's last remaining civilian research reactor, and its present core is soon to be removed. This study examines the feasibility of re-using the reactor facility for accelerator-driven systems research by replacing the fuel and installing a spallation neutron target driven by an external proton accelerator. MCNP5/MCNPX were used to model alternative, high-density fuels and their coupling to the neutrons generated by 230 MeV protons from a cyclotron striking a solid tungsten spallation target side-on to the core. Low-enriched U 3 Si 2 and U-9Mo were considered as candidates, with only U-9Mo found to be feasible in the compact core; fuel element size and arrangement were kept the same as the original core layout to minimise thermal hydraulic and other changes. Reactor thermal power up to 2.5 kW is predicted for a k ef f of 0.995, large enough to carry out reactor kinetic experiments.

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Concept of a dual-purpose electronuclear plant

Bergel'son¹,

Balyuk²

1996

At Energy

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Electronuclear plants have been under development without any visible success for many years. The main difficulties in this direction of development of nuclear power were associated with the high cost of the accelerator and the absence of a characteristic "niche" in the nuclear-power complex. In the last few years, however, the situation has largely changed --the safety standards for nuclear power plant operauon and burial of radioactive wastes have been made more stringent. It seems that the solution of these complicated problems, on which the future of nuclear power largely depends, can be found in the use of dual-purpose electronuclear plants within a nuclear-power complex for the production of electricity and for transmutation (annihilation) of long-lived radiotoxicity, determined mainly by Np, Am, and Cm produced in power reactors [1].In the present article, we present the results of conceptual investigations of a dual-purpose electronuclear plant operating on liquid fuel under the conditions of the uranium-plutonium fuel cycle.Let us examine in the equilibrium regime a dual-purpose electronuclear plant, whose blanket is f'dled with the working medium (liquid fuel) and is replenished with 238U (or natural uranium) and Np, Am, and Cm. Let ql and q2 be the specific rate of replenishment, which is constant in time, of the blanket with 238U and Np, Am, and Cm, respectively. Then the neutron multiplication factor in a homogeneous medium containing an equilibrium actinide density can be determined as follows:In Eq. (1) v t and Pl are, respectively, the number of neutrons produced and consumed in removing one 238U nucleus (actually, these quantities do not depend on the flux ~ of the thermal neutrons); ~' 2 and P2 are the analogous quantities for the annihilation of Np, Am, and Cm (the functions ~2(e,p) and p2(ecp) are defined in [2]); e is the relative time during which the working medium containing Np, Am, and Cm resides in the irradiation zone; E c is the macroscopic effective cross section for parasitic neutron capture in the fission products and in the medium (no actinides) f'dling the blanket; EF is the energy released in the fmsioning of one actinide nucleus; and, qv is the specific energy release in the working medium.Calculations of K~, using the formula (1) were performed for q, = 100 kW/liter, ql + q2 = 3.13"1012 nuclei/(cm3.sec) (-40 kg/(m3.yr)) and E c = 1.26-10 -4 cm -I, which corresponds to the absorption of thermal neutrons in I)20 with an admixture of 0. 1% light water and a low concentration of fission products, which are constantly removed from the medium in a special purification system [2]. The cross sections and resonance integrals were taken from [3]. Figures I and 2 display the functions K**(~) for e = 1 and 0.5 for different value of q2/ql. Essentially the same results are obtained when natural uranium is substituted for 238U.It follows from the calculations that for an equilibrium solution (suspension) of uranium and Np, Am, and Cm in heavy water with different values of q2/ql K~, <_ 1 (Ko...

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Neutron yields from proton-induced spallation reactions in thick targets of lead

Cited by 11 publications

References 10 publications

Target Studies for the Production of Lithium8 for Neutrino Physics Using a Low Energy Cyclotron

Target Studies for the Production of Lithium8 for Neutrino Physics Using a Low Energy Cyclotron

Steady-state neutronic analysis of converting the UK CONSORT reactor for ADS experiments

Concept of a dual-purpose electronuclear plant

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