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Merck
CN

01-2790

Aluminum nitrate nonahydrate

JIS special grade, ≥98.0%

Synonym(s):

Aluminium nitrate

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About This Item

Linear Formula:
Al(NO3)3 · 9H2O
CAS Number:
7784-27-2
Molecular Weight:
375.13
UNSPSC Code:
12352311
PubChem Substance ID:
329747240
EC Number:
236-751-8
MDL number:
MFCD00149132

Key Documents

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InChI key

SWCIQHXIXUMHKA-UHFFFAOYSA-N

InChI

1S/Al.3NO3.9H2O/c;3*2-1(3)4;;;;;;;;;/h;;;;9*1H2/q+3;3*-1;;;;;;;;;

SMILES string

O.O.O.O.O.O.O.O.O.[Al+3].[O-][N+]([O-])=O.[O-][N+]([O-])=O.[O-][N+]([O-])=O

grade

JIS special grade

assay

≥98.0%

form

solid

reaction suitability

reagent type: catalyst
core: aluminum

availability

available only in Japan

pH

2.5-3.5 (25 °C, 50 g/L)

mp

73 °C (lit.)

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Related Categories

pictograms

Corrosion
GHS05

signalword

Danger

hcodes

H318

Hazard Classifications

Eye Dam. 1

Storage Class

13 - Non Combustible Solids

wgk

WGK 1

flash_point_f

does not flash

flash_point_c

does not flash

ppe

dust mask type N95 (US), Eyeshields, Gloves, type P3 (EN 143) respirator cartridges

Regulatory Information

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Certificates of Analysis (COA)

Lot/Batch Number
U3533
U1050
U5448
U0948
U8669

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Carlos Rodríguez-Abreu et al.
Journal of colloid and interface science, 340(2), 254-260 (2009-10-10)
A study on the phase behavior and structure of the alkanolamine salts of the dimeric amphiphile 3,4-bis-dodecyloxycarbonyl-hexanedioic acid (GS-H) is presented for the first time. Data are compared to those of the corresponding monomeric surfactant (lauric acid, LA). The alkanolamine
Hwan-Seo Park et al.
Environmental science & technology, 41(21), 7536-7542 (2007-11-30)
The molten salt waste from a pyroprocess to recover uranium and transuranic elements is one of the problematic radioactive wastes to be solidified into a durable wasteform for its final disposal. By using a novel method, named as the GRSS
Asako Fujiwara et al.
Journal of chromatography. A, 1140(1-2), 163-167 (2006-12-13)
Extraction chromatography with commercially available UTEVA resin (for uranium and tetravalent actinide) was applied for the separation of Th and U from control solutions prepared from a multi-element control solution and from sample solutions of solidified simulated waste. Thorium and
Daniel R McAlister et al.
Health physics, 101(2), 176-179 (2011-06-29)
Rapid methods for the isolation and analysis of individual actinides (Th, U, Pu, Am/Cm) and Sr, Tc and Po from small volumes of raw urine have been developed. The methods involve acidification of the sample and the addition of aluminum
Hwan-Seo Park et al.
Environmental science & technology, 41(4), 1345-1351 (2007-06-28)
The volatilization of radionuclides during the stabilization/solidification of radioactive wastes at high temperatures is one of the major problems to be considered in choosing suitable wasteforms, process, material systems, etc. This paper reports a novel method to convert volatile wastes
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