ACCURATE NUCLEAR FUEL BURNUP ANALYSES. Fifth Quarterly Progress Report, December 1962-February 1963

Technical Report · Fri Mar 01 04:00:00 EST 1963

OSTI ID:4699625

Rider, B F; Ruiz, C P; Peterson, Jr, J P

The development of accurate methods for determination of nuclear fuel burnup is discussed. Foils of U/sup 233/, U/sup 235/, and Pu/sup 239/ were irradiated in MTR and are being irradiated in VBWR in order to measure relative fission yields of specific fission products for those isotopes. In order to measure relative fission yields of the same fission products in Th/sup 232/ and U/sup 238/, capsules are being made to contain cadmium oxide covered UO/sub 2/ and ThO/sub 2/ for irradiation in VBWR. A four column separations scheme was developed for separation of stable fission product neodymium from irradiated UO/ sub 2/. The first column of Dowex-2 is used to remove bulk quantities of U and Pu to prevent overloading of later columns. The second column of D2EHP-VYNS is used to remove Ce-144 activity. The third column of D2EHP-VYNS is used to isolate neodymium by reversed phase partition chromatography. The final column of Dowex-50 removes traces of actinides. Equations and their derivations are presented for Nd calculations. (auth)

• Research Organization: General Electric Co. Vallecitos Atomic Lab., San Jose, Calif.
• NSA Number: NSA-17-019928
• OSTI ID: 4699625
• Report Number(s): GEAP-4201
• Country of Publication: United States
• Language: English

Related Subjects

ACTINIDES
BURNUP
CADMIUM OXIDES
CERIUM 144
CHEMISTRY
CHROMATOGRAPHY
DOWEX
EQUATIONS
EXTRACTION COLUMNS
FISSION PRODUCTS
FOILS
FUEL CANS
FUELS
ION EXCHANGE MATERIALS
IRRADIATION
ISOTOPE SEPARATION
NEODYMIUM
PLUTONIUM 239
QUANTITATIVE ANALYSIS
SEPARATION PROCESSES
THORIUM OXIDES
TRACE AMOUNTS
URANIUM 233
URANIUM 235
URANIUM DIOXIDE