Comparisons of calculated and measured {sup 237}Np, {sup 241}Am, and {sup 243}Am concentrations as a function of the {sup 240}Pu/{sup 239}Pu isotopic ratio in spent fuel
The Los Alamos National Laboratory (LANL) has developed a system for determining {sup 237}Np, {sup 241}Am, and {sup 243}Am concentrations in spent fuel from measurements of the {sup 240}Pu/{sup 239}Pu isotopic ratio using calculations performed with the HELIOS lattice-physics code. Benchmark calculations for several pressurized water reactors (PWRs) were performed and compared to measured values from the literature for fuels with burnups ranging from 0 to 50,000 MWd/tonne U. A direct correlation can be found between the {sup 240}Pu/{sup 239}Pu isotopic ratio and the higher-actinide concentrations for each fuel type. Comparisons of calculated with measured values suggests that the LANL technique would yield {sup 237}Np and {sup 241}Am concentrations within {+-}5% and {sup 243}Am concentrations within {+-}15% for PWRs. Expanding this system for all reprocessing applications will require more measured data (especially for boiling water reactors and VVER-type reactors), but the existing results show a marked improvement over the previous ORIGEN calculations. Also, a better determination of the {sup 243}Am concentrations may support a greater confidence in the calculated results or suggest an alteration to the existing nuclear data. The present state of these neutronics calculations suggests that the technology exists to reduce the need for direct measurement of the {sup 237}Np, {sub 241}Am, and {sup 243}Am concentrations in spent fuel.
- Research Organization:
- Los Alamos National Laboratory, NM (US)
- Sponsoring Organization:
- US Department of Energy
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 20005566
- Journal Information:
- Nuclear Technology, Journal Name: Nuclear Technology Journal Issue: 3 Vol. 128; ISSN 0029-5450; ISSN NUTYBB
- Country of Publication:
- United States
- Language:
- English
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