Apparatus and method for quantitative assay of generic transuranic wastes from nuclear reactors
A combination of passive and active neutron measurements which yields quantitative information about the isotopic composition of transuranic wastes from nuclear power or weapons material manufacture reactors is described. From the measurement of prompt and delayed neutron emission and the incidence of two coincidentally emitted neutrons from induced fission of fissile material in the sample, one can quantify /sup 233/U, /sup 235/U and /sup 239/Pu isotopes in waste samples. Passive coincidence counting, including neutron multiplicity measurement and determination of the overall passive neutron flux additionally enables the separate quantitative evaluation of spontaneous fission isotopes such as /sup 240/Pu, /sup 244/Cm and /sup 252/Cf, and the spontaneous alpha particle emitter /sup 241/Am. These seven isotopes are the most important constituents of wastes from nuclear power reactors and once the mass of each isotope present is determined by the apparatus and method of the instant invention, the overall alpha particle activity can be determined to better than 1 nCi/g from known radioactivity data. Therefore, in addition to the quantitative analysis of the waste sample useful for later reclamation purposes, the alpha particle activity can be determined to decide whether permanent low-level burial is appropriate for the waste sample.
- DOE Contract Number:
- W-7405-ENG-36
- Assignee:
- ERA-08-017422; EDB-83-048395
- Application Number:
- ON: DE83006885
- OSTI ID:
- 6509200
- Country of Publication:
- United States
- Language:
- English
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Apparatus and method for quantitative assay of generic transuranic wastes from nuclear reactors
CHEMISTRY DIVISION SEMIANNUAL REPORT FOR DECEMBER 1957 THROUGH MAY 1958
Related Subjects
37 INORGANIC
ORGANIC
PHYSICAL AND ANALYTICAL CHEMISTRY
ALPHA-BEARING WASTES
ISOTOPE RATIO
AMERICIUM 241
NUCLEAR REACTION ANALYSIS
CALIFORNIUM 252
CURIUM 244
PLUTONIUM 239
DELAYED NEUTRON ANALYSIS
PLUTONIUM 240
URANIUM 233
URANIUM 235
FISSILE MATERIALS
PROMPT NEUTRONS
QUANTITATIVE CHEMICAL ANALYSIS
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
AMERICIUM ISOTOPES
BARYONS
CALIFORNIUM ISOTOPES
CHEMICAL ANALYSIS
CURIUM ISOTOPES
ELEMENTARY PARTICLES
EVEN-EVEN NUCLEI
EVEN-ODD NUCLEI
FERMIONS
FISSION NEUTRONS
FISSIONABLE MATERIALS
HADRONS
HEAVY NUCLEI
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
MATERIALS
MINUTES LIVING RADIOISOTOPES
NEUTRONS
NONDESTRUCTIVE ANALYSIS
NUCLEI
NUCLEONS
ODD-EVEN NUCLEI
PLUTONIUM ISOTOPES
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
RADIOISOTOPES
URANIUM ISOTOPES
WASTES
YEARS LIVING RADIOISOTOPES
052001* - Nuclear Fuels- Waste Processing
400101 - Activation
Nuclear Reaction
Radiometric & Radiochemical Procedures