منابع مشابه
Neutron-induced deuteron production from light nuclei at 800 MeV
The deuteron sepctra from {n,d) reactions at 800 MeV near 0' are characterized by a high energy quasielastic scattering peak, and at lower momentum, a quasifree scattering peak. The ratio of the quasifree to quasielastic cross sections is approximately 10:1.Both cross sections exhibit an A '" mass dependence over the range of target nuclei studied. Comparisons are made with corresponding proton...
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Lawrence Berkeley National Laboratory, Berkeley, CA 94720, U.S.A. BEARS is an ongoing project to provide a light-ion radioactive-beam capability at the 88-Inch Cyclotron at LBNL. Light radioactive isotopes are produced at a 10 MeV proton medical cyclotron, transported 350 m via a high-speed gas transport capillary, cryogenically separated, and injected into the 88-Inch Cyclotron’s ion source. T...
متن کاملMeV Neutron Generator – Literature Review
A 14 MeV neutron generator described in this paper.Neutrons are produced in D-T, D-D,T-T reactions. The production of 14 MeV neutrons from DD neutrons generator resulting from tritium build up from d(d,p)t reaction in the target under 30mA, 300 KeV deuteron beam, bombarding a water-cooled, rotating target, size of beam spot on target is 1.8 cm is obtained. An estimate of the capital cost 14 MeV...
متن کاملFeasibility Study and Installation of Thermal Neutron Driven 14 MeV Neutron Converter into the TRIGA Research Reactor
Tentative design and implementation of an irradiation facility are described, which will add a 14 MeV component to the neutron spectrum in a thermal research reactor irradiation facility. The idea is to exploit the Li(n,T)He reaction in a blanket of lithium in a deuterated environment, placed in a thermal reactor irradiation channel. Existing literature describing similar devices is reviewed, t...
متن کاملMonte Carlo Calculations Using MCNP4B for an Optimal Shielding Design of a 14-MeV Neutron Source
The shielding for 14-MeV neutrons from a D-T generator at SLAC needs to be optimized in terms of shield thickness and cost. Shielding calculations were made using the MCNP4B Monte Carlo code and the ENDF/B-VI cross section set. A few materials were studied: iron, borated polyethylene, three types of normal and heavy concrete, and mixtures of iron and borated polyethylene. The effects of shieldi...
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ژورنال
عنوان ژورنال: Journal of Neutron Research
سال: 2020
ISSN: 1477-2655,1023-8166
DOI: 10.3233/jnr-190140