Patents by Inventor Iain May

Iain May has filed for patents to protect the following inventions. This listing includes patent applications that are pending as well as patents that have already been granted by the United States Patent and Trademark Office (USPTO).

  • Patent number: 9842664
    Abstract: A processes for recycling uranium that has been used for the production of molybdenum-99 involves irradiating a solution of uranium suitable for forming fission products including molybdenum-99, conditioning the irradiated solution to one suitable for inducing the formation of crystals of uranyl nitrate hydrates, then forming the crystals and a supernatant and then separating the crystals from the supernatant, thus using the crystals as a source of uranium for recycle. Molybdenum-99 is recovered from the supernatant using an adsorbent such as alumina. Another process involves irradiation of a solid target comprising uranium, forming an acidic solution from the irradiated target suitable for inducing the formation of crystals of uranyl nitrate hydrates, then forming the crystals and a supernatant and then separating the crystals from the supernatant, thus using the crystals as a source of uranium for recycle. Molybdenum-99 is recovered from the supernatant using an adsorbent such as alumina.
    Type: Grant
    Filed: September 26, 2013
    Date of Patent: December 12, 2017
    Assignee: Los Alamos National Security, LLC
    Inventors: Sean Douglas Reilly, Iain May, Roy Copping, Gregory Edward Dale
  • Patent number: 9793023
    Abstract: A process for minimizing waste and maximizing utilization of uranium involves recovering uranium from an irradiated solid target after separating the medical isotope product, molybdenum-99, produced from the irradiated target. The process includes irradiating a solid target comprising uranium to produce fission products comprising molybdenum-99, and thereafter dissolving the target and conditioning the solution to prepare an aqueous nitric acid solution containing irradiated uranium. The acidic solution is then contacted with a solid sorbent whereby molybdenum-99 remains adsorbed to the sorbent for subsequent recovery. The uranium passes through the sorbent. The concentrations of acid and uranium are then adjusted to concentrations suitable for crystallization of uranyl nitrate hydrates. After inducing the crystallization, the uranyl nitrate hydrates are separated from a supernatant. The process results in the purification of uranyl nitrate hydrates from fission products and other contaminants.
    Type: Grant
    Filed: September 30, 2013
    Date of Patent: October 17, 2017
    Assignee: Los Alamos National Security, LLC
    Inventors: Sean Douglas Reilly, Iain May, Roy Copping, Gregory Edward Dale
  • Publication number: 20150085964
    Abstract: A process for minimizing waste and maximizing utilization of uranium involves recovering uranium from an irradiated solid target after separating the medical isotope product, molybdenum-99, produced from the irradiated target. The process includes irradiating a solid target comprising uranium to produce fission products comprising molybdenum-99, and thereafter dissolving the target and conditioning the solution to prepare an aqueous nitric acid solution containing irradiated uranium. The acidic solution is then contacted with a solid sorbent whereby molybdenum-99 remains adsorbed to the sorbent for subsequent recovery. The uranium passes through the sorbent. The concentrations of acid and uranium are then adjusted to concentrations suitable for crystallization of uranyl nitrate hydrates. After inducing the crystallization, the uranyl nitrate hydrates are separated from a supernatant. The process results in the purification of uranyl nitrate hydrates from fission products and other contaminants.
    Type: Application
    Filed: September 30, 2013
    Publication date: March 26, 2015
    Applicant: LOS ALAMOS NATIONAL SECURITY, LLC
    Inventors: Sean Douglas REILLY, Iain MAY, Roy Copping, Gregory Edward DALE
  • Publication number: 20150085963
    Abstract: A processes for recycling uranium that has been used for the production of molybdenum-99 involves irradiating a solution of uranium suitable for forming fission products including molybdenum-99, conditioning the irradiated solution to one suitable for inducing the formation of crystals of uranyl nitrate hydrates, then forming the crystals and a supernatant and then separating the crystals from the supernatant, thus using the crystals as a source of uranium for recycle. Molybdenum-99 is recovered from the supernatant using an adsorbent such as alumina. Another process involves irradiation of a solid target comprising uranium, forming an acidic solution from the irradiated target suitable for inducing the formation of crystals of uranyl nitrate hydrates, then forming the crystals and a supernatant and then separating the crystals from the supernatant, thus using the crystals as a source of uranium for recycle. Molybdenum-99 is recovered from the supernatant using an adsorbent such as alumina.
    Type: Application
    Filed: September 26, 2013
    Publication date: March 26, 2015
    Applicant: Los Alamos National Security, LLC
    Inventors: Sean Douglas REILLY, Iain MAY, Roy COPPING, Gregory Edward Dale
  • Patent number: 6444182
    Abstract: The spent nuclear fuel reprocessing method includes contacting an organic phase containing Np(VI) with a hydrophilic substituted hydroxylamine in which at least one N—H hydrogen of the hydroxylamine is replaced by an organic substituent, there being at least one such organic substituent having one or more hydroxyl groups. Np(VI) is reduced to Np(V), which is then backwashed into an aqueous phase.
    Type: Grant
    Filed: July 11, 2000
    Date of Patent: September 3, 2002
    Assignee: British Nuclear Fuels plc
    Inventors: Sergey Mikhailovich Baranov, Valentin Sergeevich Koltunov, Robin John Taylor, Iain May
  • Patent number: 6413482
    Abstract: A spent nuclear fuel reprocessing method includes contacting an organic phase containing NP(VI) with an oxime of the formula R2C═NOH, where each R is independently H or an organic substituent. Np(VI) is reduced to Np(V) which is then backwashed into an aqueous phase.
    Type: Grant
    Filed: July 11, 2000
    Date of Patent: July 2, 2002
    Assignee: British Nuclear Fuels plc
    Inventors: Sergey Mikhailovich Baranov, Valentin Sergeevich Koltunov, Eduard Andreevich Mezhov, Robin John Taylor, Iain May, Victor Georgievich Pastuschak
  • Patent number: 6196052
    Abstract: A piezoelectric gas sensing device, comprising: (a) a piezoelectric element arranged for gas sensing exposure to a gas environment; (b) a layer of a gas-retentive support material on the piezoelectric element which is retentively effective for a gas component potentially present in the gas environment; and (c) a gas-interactive material associated with the retentive support material, and sorptively effective to form a solid interaction product in interaction with the gas component potentially present in the gas environment, with the solid interaction product imparting a changed frequency response to the piezoelectric gas sensing device, in relation to a corresponding piezoelectric gas sensing device in the absence of the solid interaction product resulting from presence of the gas component in the gas environment. The device can be utilized to detect the presence and/or concentration of a gas species such as a hydride, hydrocarbon, silane, etc. in the fluid being monitored by the device.
    Type: Grant
    Filed: October 5, 1998
    Date of Patent: March 6, 2001
    Assignee: Advanced Technology Materials, Inc.
    Inventors: Iain May, Glenn M. Tom