MASS-SPECTROMETRIC STUDIES OF PILE POISONS AND THEIR YIELDS IN THE FISSION OF U-233, U-235, AND Pu-239
Technical Report
·
OSTI ID:4264936
obtained at various neutron fluxes and irradiation times has made possible the measurement of pileneutron absorption resulting from the accumulation of several fission products in a D/sub 2/O-moderated reactor. The following pile-neutron absorption cross sections have been measured relative to Co/sup 59/ = 36.0 barns: Cs/sup 133/ = 40 barns, Pm/sup 147/ = 207 barns, Sm/sup 149/ = 85,000 barns, Sm/sup 151/ = 11,500 barns. Some of these values are considerably higher than thermal-neutron values because of resonance absorption. Cumulative yields of each of these nuclides as well as those of the 135 and 143 mass chains have also been measured by isotopedilution techniques for the thermal- neutron fission of U/sup 233/ and Pu /sup 239/. These measurements, together with the previously published cross section of Xe/sup 135/ and fission yields for U/sup 235/, make possible a comparison of these poisons in reactors using U/sup 233/, U/sup 235/, and Pu/sup 239/ fuels. In twenty-three mass chains where the stable or longlived end products have low absorption cross sections, it has been possible to eliminate the possibility of significant neutron absorption amongst the short-lived precursors. (auth)
- Research Organization:
- McMaster Univ., Hamilton, Ont.
- NSA Number:
- NSA-13-006962
- OSTI ID:
- 4264936
- Report Number(s):
- A/CONF.15/P/201; AECL-611
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
Similar Records
FISSION RESONANCE INTEGRALS OF U-233, U-235, Pu-239, AND Pu-241
ENERGY-DEPENDENT AND SPECTRUM-AVERAGED THERMAL CROSS SECTIONS FOR THE HEAVY ELEMENTS AND FISSION PRODUCTS FOR VARIOUS TEMPERATURES AND C: U$sup 235$ ATOM RATIOS
Measurement of the neutron capture and fission cross sections of $sup 239$Pu and $sup 235$U, 0.02 eV to 200 keV, the neutron capture cross sections of $sup 197$Au, 10 to 50 keV, and neutron fission cross sections of $sup 233$U, 5 to 200 keV
Technical Report
·
Fri Jan 31 23:00:00 EST 1964
·
OSTI ID:4008097
ENERGY-DEPENDENT AND SPECTRUM-AVERAGED THERMAL CROSS SECTIONS FOR THE HEAVY ELEMENTS AND FISSION PRODUCTS FOR VARIOUS TEMPERATURES AND C: U$sup 235$ ATOM RATIOS
Technical Report
·
Fri Jun 16 00:00:00 EDT 1961
·
OSTI ID:4841912
Measurement of the neutron capture and fission cross sections of $sup 239$Pu and $sup 235$U, 0.02 eV to 200 keV, the neutron capture cross sections of $sup 197$Au, 10 to 50 keV, and neutron fission cross sections of $sup 233$U, 5 to 200 keV
Journal Article
·
Sat Jan 31 23:00:00 EST 1976
· Nucl. Sci. Eng., v. 59, no. 2, pp. 79-105
·
OSTI ID:4093952
Related Subjects
ABSORPTION
CESIUM 133
COBALT 59
CROSS SECTIONS
FISSION
FISSION PRODUCTS
FUELS
HEAVY WATER
IRRADIATION
ISOTOPES
MASS
MASS SPECTROMETERS
MEASURED VALUES
MODERATORS
NEUTRON FLUX
NEUTRONS
PHYSICS AND MATHEMATICS
PLUTONIUM 239
POISONING
PRODUCTION
PROMETHIUM 147
REACTORS
RESONANCE
SAMARIUM 149
SAMARIUM 151
STANDARDS
THERMAL NEUTRONS
URANIUM 233
URANIUM 235
XENON 135
CESIUM 133
COBALT 59
CROSS SECTIONS
FISSION
FISSION PRODUCTS
FUELS
HEAVY WATER
IRRADIATION
ISOTOPES
MASS
MASS SPECTROMETERS
MEASURED VALUES
MODERATORS
NEUTRON FLUX
NEUTRONS
PHYSICS AND MATHEMATICS
PLUTONIUM 239
POISONING
PRODUCTION
PROMETHIUM 147
REACTORS
RESONANCE
SAMARIUM 149
SAMARIUM 151
STANDARDS
THERMAL NEUTRONS
URANIUM 233
URANIUM 235
XENON 135