Abstract: The current invention relates to a method of separating polyunsaturated fatty acids containing lipids from a lipids containing biomass.

Abstract: This invention relates to a method of using a two-step serial centrifugation process in extracting nutritive oil from a fermentation broth, this novel method prevents oil yield losses while preserving product quality.

Abstract: A storage apparatus is provided for dry storage of radioactive nuclear waste. The storage apparatus comprises a sealed canister containing the radioactive nuclear waste and an outer ventilated metal storage overpack (VMSO). The VMSO has a plurality of vents to enable ambient air flow through the VMSO and around the canister to thereby dissipate heat from the canister. The VMSO has a side wall having an inner metal layer and one or more sets of alternating layers. Each set includes a neutron absorbing layer adjacent to another metal layer so that neutron absorbing and metal layers alternate throughout the side wall. The neutron absorbing layer or layers are designed to absorb neutron particles radiated from the radioactive nuclear waste and the metal layers are designed to absorb gamma particles radiated from the radioactive nuclear waste as well as radiated from the neutron absorbing layer or layers that result from reactions associated with absorption of neutron particles.

Abstract: The current invention relates to a method of isolating polyunsaturated fatty acids containing lipids from a lipids containing biomass. The method involves providing a suspension of cells with a PUFAs-containing lipid; optionally lysing the cells; concentrating the suspension; adding base equivalents to the suspension based on the total dry matter present; feeding a continuous reactor with the suspension; and separating the lipids-containing light phase from the water and cell debris-containing heavy phase.

Abstract: The invention relates to the isolation of polyunsaturated fatty acids (PUFAs) from a lipids containing biomass. The main characteristics of the method are that a suspension of cells containing PUFAs is obtained and the cells are optionally lysed. The suspension is concentrated and then incubated for at least an hour at a controlled temperature while adding a specific range of base equivalents to biomass and maintaining a moderate pH. The isolation of lipid may be performed in the absence of organic solvents and without the addition of salt.

Abstract: The current invention relates to a method of separating polyunsaturated fatty acids containing lipids from a lipids containing biomass by using acetone.

Abstract: This invention relates to a method of using a two-step serial centrifugation process in extracting nutritive oil from a fermentation broth, this novel method prevents oil yield losses while preserving product quality.

Abstract: The current invention relates to a method of isolating polyunsaturated fatty acids containing lipids from a lipids containing biomass comprising a step of demulsification in a continuous reactor.

Abstract: The current invention relates to a method of separating polyunsaturated fatty acids containing lipids from a lipids containing biomass.

Abstract: The current invention relates to a method of separating polyunsaturated fatty acids containing lipids from a lipids containing biomass by using acetone.

Abstract: The current invention relates to a method of isolated polyunsaturated fatty acids containing lipids from a lipids containing biomass.

Abstract: The current invention relates to a method for isolating polyunsaturated fatty acids containing lipids from lipid-containing cells.

Abstract: The processes for obtaining a microbial oil comprising one or more polyunsaturated fatty acids (PUFAs) from one or more microbial cells comprise removing water from the cell fermentation broth or lysed cell composition before demulsification is conducted. Such a process has the benefits of reduced demulsification time and reduced salt use. Microbial oil comprising one or more PUFAs can be recovered from microbial cells by the process.

Abstract: A storage apparatus is provided for dry storage of radioactive nuclear waste. The storage apparatus comprises a sealed canister containing the radioactive nuclear waste and an outer ventilated metal storage overpack (VMSO). The VMSO has a plurality of vents to enable ambient air flow through the VMSO and around the canister to thereby dissipate heat from the canister. The VMSO has a side wall having an inner metal layer and one or more sets of alternating layers. Each set includes a neutron absorbing layer adjacent to another metal layer so that neutron absorbing and metal layers alternate throughout the side wall. The neutron absorbing layer or layers are designed to absorb neutron particles radiated from the radioactive nuclear waste and the metal layers are designed to absorb gamma particles radiated from the radioactive nuclear waste as well as radiated from the neutron absorbing layer or layers that result from reactions associated with absorption of neutron particles.

Abstract: The present invention relates to a liquid coating composition comprising i) at least one inorganic binder of the generic formula SiaR1bOc(OR2)d with a?2, b?0, c?1, d?5 and R1 and R2=organic radical, ii) at least one solvent and iii) at least one oxide pigment which, after addition of a mixture consisting of 15 ml of 1 M oxalic acid and 15 ml of 20% aqueous hydrochloric acid, based on 1 g of substance, under standard conditions, leads to a temperature rise of at least 4° C., to processes for preparation thereof and to the use thereof.

Abstract: A transfer cask system for cooling spent nuclear fuel during the transfer from a spent nuclear fuel pool to a storage or transfer cask is disclosed. A canister containing spent nuclear fuel is inserted into a transfer cask. The transfer cask includes spacing components which define an annular region between the transfer cask and the canister. The transfer cask includes air inlets near a bottom end that permit air to flow through the defined annular region and exit at the open top of the transfer cask, thereby cooling the fuel within the canister. The transfer cask further comprises a neutron shield configured to absorb additional heat and shield radiation that may be generated within the canister. The transfer cask includes a transfer door that can open and close and has support rails that can support a spent nuclear fuel canister located in the transfer cask.

Abstract: Systems and methods of cooling spent nuclear fuel during the transfer from a spent nuclear fuel pool to a storage or transfer cask are disclosed. A canister containing spent nuclear fuel is inserted into a transfer cask. The transfer cask includes spacing components which define an annular region between the transfer cask and the canister. The transfer cask includes air inlets near a bottom end that permit air to flow through the defined annular region and exit at the open top of the transfer cask, thereby cooling the fuel within the canister. The transfer cask further comprises a neutron shield configured to absorb additional heat and shield radiation that may be generated within the canister. The spent nuclear fuel canister is then transferred from the transfer cask to a storage cask or a transport cask for storage in an on-site or in an off-site storage facility.