Specialty chemicals for the nuclear energy industry

Marshallton manufactures specialty chemicals for remediation and recycling in the nuclear energy industry. These include MAXCalix extractant, CS-7SB solvent modifier, and guanidine suppressors, key components for cesium removal. Also available are extractants and solvents used in nuclear fuel cycle R & D and analytical reagents.

Marshallton continues to develop new products to meet the growing needs of the nuclear industry. Please contact us about tailoring a new active ingredient or new formulation for your specific application.

Download Marshallton Research Nuclear Energy Specialties Brochure

MAXCalix, Cs-7SB Modifier, TiDG, BOBCalixC6, BEHBCalixC6


HEH[EHP], Bis-(o-Trifluoromethylphenyl)dithiophosphinic Acid





Item# MAXCalix

Compound Description: 1,3-alt-25,27-Bis(3,7-dimethyloctyloxy)calix[4]arene-benzocrown-6

CAS# [1227059-50-8]



Item# Cs-7SB Modifier

Compound Description: 1-(2,2,3,3,-Tetrafluoropropoxy)-3-(4-sec-butylphenoxy)-2-propanol

CAS# [308362-88-1]



Item# TiDG

Compound Description: N,N’,N’’-Tris(3,7-dimethyloctyl)guanidine




Item # BOBCalixC6

Compound Description:  Calix[4]arene-bis(t-octylbenzo-crown-6)

CAS#  [220969-34-6]


Item # BEHBCalixC6

Compound Descripition:  Calix[4]arene-bis(2ethylhexylbenzo-crown-6)

CAS# [757196-34-2]


Cesium extractant BOBCalixC6 was invented by Oak Ridge National Lab for the removal of cesium from aqueous salt feedstocks. Cs-7SB modifier improves the solubility of BOBCalixC6 in the formulated solvent system, and increases its effectiveness in capturing cesium ions. They are key components for Caustic-Side Solvent Extraction (CSSX)a, b and Fission-Product Extraction (FPEX)c processes. The Caustic-Side Solvent Extraction (CSSX) process has been demonstrated in plant-scale operations at the US Department of Energy’s Savannah River Sited,e.

MAXCalixf and BEHBCalixC6g are new cesium extractants with superior solubility properties and greatly improved efficiencyg,h. They can process higher-curie feeds and accommodate streams with heavier loadings of potassiumi. MAXCalix is utilized in the next-generation solvent (NGS)h,j, now in service at the Savannah River Sitek.

(a) B.A. Moyer, et al. (2001) “Calixarene crown ether solvent composition and use thereof for extraction of cesium from alkaline waste solutions”. US Patent 6,174,503.

(b) L.H. Delmau, et al. (2002) “Caustic-Side Solvent Extraction: chemical and physical properties of the optimized solvent” Oak Ridge National Lab Report ORNL/TM-2002/190.

(c) J.Law, et al. (2008) “Simultaneous separation of cesium and strontium from spent nuclear fuel using the Fission-Product Extraction process”. Solvent Extraction: Fundamentals to Industrial Applications: Proceedings of ISEC 2008 International Solvent Extraction Conference, Vol. 1, 659-664.

(d) M.R.Poirier, et al.(2008) “Full-scale testing of a Caustic Side Solvent Extraction system to remove cesium from Savannah River site radioactive waste”. Separation Science and Technology, 43:2797-2813.

(e) E.A. Brass et al. (2008) “First plant-scale operation of Caustic-Side Solvent Extraction process for removal of cesium at the Savannah River site”. Presentation at 18th International Solvent Extraction Conference, Tucson, Arizona, September 15-19, 2008.

(f) D.R. Peterman, et al.(2012) “Extractant compositions for co-extracting cesium and strontium, A method of separating cesium and strontium from an aqueous feed, and calixarene compounds” US Patent 8,158,088.

(g) L.H. Delmau, et al.(2009) “Alternatives to nitric acid striping in the Caustic-Side Solvent Extraction (CSSX) process for cesium removal from alkaline high-level waste”. Solvent Extraction and Ion Exchange, 27:172-198.

(h) B.A. Moyer, et al.(2011) “Development of the Next-Generation Caustic-Side Solvent Extraction (NG-CSSX) process for cesium removal from high-level tank waste” WM2011 Conference Paper no. 11346.

(i) T.B.Peters, et al. (2011) “Results of Cesium Mass Transfer Testing for Next Generation Solvent with Hanford Waste Simulant AP-101”. SRNL-STI-2011-00559 Revision 0 .

(j) R. Piecer, et al. (2012) “Performance testing of the Next-Generation CSSX solvent with actual SRS tank waste”. Separation Science and Technology, 47:2088-2097.

(k) D.Campbell (2013) “SRS Salt Waste Processing: 5 Years of Success”. www.srs.gov. SRS News Releases, April 22, 2013.


Nuclear Fuel Cycle

Item# FS-13

Compound Description: Phenyl Trifluoromethyl Sulfone

CAS# [426-58-4]




Phenyl trifluoromethyl sulfone (FS-13) is used as diluent or process solvent in nuclear applications, such as the UNEX process a, the HCCD-PEG process b, and the separation of minor actinides from lanthanides c .

(a) E.K.Rzhekhina, et al. (2007) “Processing of spent solvent of the UNEX process”. Radiochemistry, 49(5): 493-498.

(b) R.S. Herbst et al. (2008) “Fundamental chemistry of cesium extraction from acidic media by HCCD in FS-13” Solvent Extraction and Ion Exchange, 26(2):163-174.

(c) D.R. Peterman, et al. (2008) “Separation of minor actinides from lanthanides by dithiophosphinic acid extractants”. Solvent Extraction: Fundamentals to Industrial Applications: Proceedings of ISEC 2008 International Solvent Extraction Conference, Vol. 2, 1427-1432.


Item # CMPO

Compound Description: Octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide

CAS# [83242-95-9]




CMPO is used as an actinides extractant in TRUEX processa.

(a) R.C. Gatrone, et al. (1987) “The synthesis and purification of the carbamoylmethylphosphine oxides”. Solvent Extraction and Ion Exchange, 5:1075-1116.



Compound Description: N,N,N’,N’-Tetraoctyl diglycolamide

CAS# [342794-43-8]




Compound Description: N,N,N’,N’-Tetra(2-ethylhexyl) diglycolamide

CAS# [669087-46-1]



Item# DOODA(C2)

Compound Description: N, N,N’,N’-Tetraethyl-3,6-dioxaoctanediamide

CAS# [73796-39-1]


Item# CyMe4-BTBP

Compound Description: 6,6’-Bis(5,5,8,8-tetramethyl-5,6,7,8-tetrahydro-benzo[1,2,4]triazin-3-yl)-2,2’-bipyridine



Item# HEH[EHP]

Compound Description: 2-Ethylhexylphosponic acid -2-ethylhexyl ester

CAS# [14802-03-0]


Item #: 50175

Compound Description: Bis(o-Trifluoromethylphenyl)dithiophosphinic acid


TODGA(a,b,c),T2EHDGA(c,d),DOODA(C2)(e),HEH[EHP](f),CyMe4-BTBP(g), and Bis(o-Trifluoromethylphenyl)dithiophosphinic acid(h) are examples of different classes of extractants with applications in the separation of lanthanides and actinides.

(a) S.A. Ansari, et.al. (2005) “N,N,N’,N’-tetraoctyl diglycolamide (TODGA) : a promising extractant for actinide-partitioning from high-level waste (HLW)” Solvent Extraction and Ion Exchange 23(4): 463-479

(b) X. Sun; et.al. (2012) “Ionic liquids-based extraction: a promising strategy for the advanced nuclear fuel cycle” Chem. Rev. 112(4):2100-2128

(c) A.V. Gelis, et.al. (2014) “Actinide lanthanide separation process-ALSEP” Industrial & Engineering Chemistry Research, 53:1624-1631

(d) R.B. Gujar, et.al. (2010) “Development of T2EHDGA based process for actinide partitioning. Part I: Batch studies for process optimization” Solvent Extraction and Ion Exchange, 28(3):350-366

(e) Y.Sasaki, et.al. (2011) “Separation of Am, Cm, and lanthanides by solvent extraction with hydrophilic and lipophilic organic ligands” Solvent Extraction Research and Development, Japan, Vol. 18:93-101

(f) G.J.Lumetta (2010) “Review: Solvent systems combining neutral & acidic extractants for separating trivalent lanthanides from the transuranic elements” Solvent Extraction and Ion Exchange 28(3): 287-312

(g) A.Geist, et.al. (2006) “6,6′-Bis(5,5,8,8-tetramethyl-5,6,7,8-tetrahydro-benzo[1,2,4]triazin-3yl)-2,2′-bipyridine: an effective extracting agent for the separation of Americium(III) and curium(III) from the lanthanides” Solvent Extraction and Ion Exchange 24(4): 463-483

(h) J.R.Klaehan, et al. (2008) “Synthesis of symmetric dithiophosphinic acids for “minor actinide” extraction”. Inorganica Chimica Acta 361: 2522-2532.


 Analytical Reagents

Item # HBQS

Compound Description: 10-Hydroxybenzo[h]quinoline-7-sulfonate


10-Hydroxybenzo[h]quinoline-7-sulfonate (HBQS) is used as a fluorescence reagent for determination of beryllium with high sensitivity and selectivity. NIOSH Methods 7704 and 9110 detail analytical procedures which are readily adaptable to field testing conditions.


Item #   DDCP

Compound Description: Dibutyl-N,N-diethylcarbamoyl phosphonate

CAS# [7439-69-2]


DDCP is an analytical reagent for detection of Pu and Am.