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19734-51-1

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19734-51-1 Usage

Check Digit Verification of cas no

The CAS Registry Mumber 19734-51-1 includes 8 digits separated into 3 groups by hyphens. The first part of the number,starting from the left, has 5 digits, 1,9,7,3 and 4 respectively; the second part has 2 digits, 5 and 1 respectively.
Calculate Digit Verification of CAS Registry Number 19734-51:
(7*1)+(6*9)+(5*7)+(4*3)+(3*4)+(2*5)+(1*1)=131
131 % 10 = 1
So 19734-51-1 is a valid CAS Registry Number.

19734-51-1SDS

SAFETY DATA SHEETS

According to Globally Harmonized System of Classification and Labelling of Chemicals (GHS) - Sixth revised edition

Version: 1.0

Creation Date: Aug 20, 2017

Revision Date: Aug 20, 2017

1.Identification

1.1 GHS Product identifier

Product name 2-ethyl-N-methylhexan-1-amine

1.2 Other means of identification

Product number -
Other names (+-)-2-Aethyl-1-methylamino-hexan

1.3 Recommended use of the chemical and restrictions on use

Identified uses For industry use only.
Uses advised against no data available

1.4 Supplier's details

1.5 Emergency phone number

Emergency phone number -
Service hours Monday to Friday, 9am-5pm (Standard time zone: UTC/GMT +8 hours).

More Details:19734-51-1 SDS

19734-51-1Downstream Products

19734-51-1Relevant articles and documents

NOVEL DISSYMMETRIC N,N-DIALKYLAMIDES, THE SYNTHESIS THEREOF AND USES OF SAME

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Paragraph 0111; 0113, (2018/08/25)

Novel dissymmetric N,N-dialkylamides which meet the following formula (I): where R represents a linear or branched alkyl group at C8 to C15. A method for synthesizing these N,N-dialkylamides, and to the uses of same as extractants, alone or in admixture, in order to extract uranium and/or plutonium from an aqueous acid solution, or to totally or separate uranium from plutonium from an aqueous acid solution and, in particular, an aqueous solution resulting from dissolving spent nuclear fuel in nitric acid. Further, a method for processing an aqueous solution resulting from the dissolution of a spent nuclear fuel in nitric acid, allowing the uranium and plutonium contained in the solution to be extracted, separated and decontaminated in a single cycle, without requiring any plutonium reduction operation, and in which one of the aforementioned N,N-dialkylamides or a mixture of same is used as extractant. Applications for the method include the processing of spent nuclear fuels, in particular comprising uranium (e.g. UOX) or uranium and plutonium (e.g. MOX).

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