C07C275/06

PROCESSES FOR THE PREPARATION OF (S)-TERT-BUTYL 4,5-DIAMINO-5-OXOPENTANOATE

Provided are processes for the preparation of (S)-tert-butyl 4,5-diamino-5-oxopentanoate, or a salt, solvate, hydrate, enantiomer, mixture of enantiomers, or isotopologue thereof. Also provided are solid forms of various intermediates and products obtained from the processes.

PROCESSES FOR THE PREPARATION OF (S)-TERT-BUTYL 4,5-DIAMINO-5-OXOPENTANOATE

Provided are processes for the preparation of (S)-tert-butyl 4,5-diamino-5-oxopentanoate, or a salt, solvate, hydrate, enantiomer, mixture of enantiomers, or isotopologue thereof. Also provided are solid forms of various intermediates and products obtained from the processes.

Processes for the preparation of (S)-tert-butyl 4,5- diamino-5-oxopentanoate

Provided are processes for the preparation of (S)-tert-butyl 4,5-diamino-5-oxopentanoate, or a salt, solvate, hydrate, enantiomer, mixture of enantiomers, or isotopologue thereof. Also provided are solid forms of various intermediates and products obtained from the processes.

Processes for the preparation of (S)-tert-butyl 4,5- diamino-5-oxopentanoate

Provided are processes for the preparation of (S)-tert-butyl 4,5-diamino-5-oxopentanoate, or a salt, solvate, hydrate, enantiomer, mixture of enantiomers, or isotopologue thereof. Also provided are solid forms of various intermediates and products obtained from the processes.

Carbamides for separating uranium(VI) and plutonium(IV) without reducing the plutonium(IV)

The use of carbamides as extractants for fully or partially separating uranium(VI) from plutonium(IV) in an aqueous solution obtained by dissolving a spent nuclear fuel in nitric acid, by method of liquid-liquid extraction, without carrying out any reduction of the plutonium(IV) to plutonium(III). The invention also relates to new carbamides. Uses are the processing of spent nuclear fuels based on uranium (especially uranium oxides—UOX) or uranium and plutonium (especially mixed uranium and plutonium oxides—MOX).

Substituted Ureas and Methods of Making and Using Same
20220315567 · 2022-10-06 ·

The invention relates to substituted ureas, and compositions comprising the same, which in certain embodiments are useful for treating and/or preventing pain in a subject in need thereof.

Substituted Ureas and Methods of Making and Using Same
20220315567 · 2022-10-06 ·

The invention relates to substituted ureas, and compositions comprising the same, which in certain embodiments are useful for treating and/or preventing pain in a subject in need thereof.

Substituted ureas and methods of making and using same

The invention relates to substituted ureas, and compositions comprising the same, which in certain embodiments are useful for treating and/or preventing pain in a subject in need thereof.

Substituted ureas and methods of making and using same

The invention relates to substituted ureas, and compositions comprising the same, which in certain embodiments are useful for treating and/or preventing pain in a subject in need thereof.

CARBAMIDES FOR SEPARATING URANIUM(VI) AND PLUTONIUM(IV) WITHOUT REDUCING THE PLUTONIUM(IV)

The-use of carbamides as extractants for fully or partially separating uranium(VI) from plutonium(IV) in an aqueous solution obtained by dissolving a spent nuclear fuel in nitric acid, by method of liquid-liquid extraction, without carrying out any reduction of the plutonium(IV) to plutonium(III). The invention also relates to new carbamides. Uses are the processing of spent nuclear fuels based on uranium (especially uranium oxides—UOX) or uranium and plutonium (especially mixed uranium and plutonium oxides—MOX).