The specific ( ,n) production rate for 234U in UF6
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Univ. of Tennessee, Knoxville, TN (United States)
Natural, depleted, and low enriched uranium hexafluoride is manufactured and transported on an industrial scale to support commercial nuclear power plant operation. One-way material production and flow is verified by nuclear safeguards inspectorates is by neutron counting. The dominant neutron source term is ( ,n) production due to 234U which gets enriched/depleted along with 235U. We describe recent efforts to accurately determine the ( ,n)/s/g of 234U in UF6. This piece of nuclear data is of direct value to the nuclear safeguards community in the science-based verification and assay of bulk uranium hexafluoride. It also provides a benchmark on codes that calculate yield curves for various compounds from cross section data, and hence, provides a scale or normalization constraint on evaluated basic cross section data. Finally, in turn, evaluated basic data allows the yield from other materials to be calculated; for instance, moist uranyl fluoride, which is of interest in holdup measurements.
- Research Organization:
- Los Alamos National Laboratory (LANL), Los Alamos, NM (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Nonproliferation
- Grant/Contract Number:
- 89233218CNA000001
- OSTI ID:
- 1484670
- Alternate ID(s):
- OSTI ID: 1636239
- Report Number(s):
- LA-UR-18-29309
- Journal Information:
- Nuclear Instruments and Methods in Physics Research. Section A, Accelerators, Spectrometers, Detectors and Associated Equipment, Vol. 954; ISSN 0168-9002
- Publisher:
- ElsevierCopyright Statement
- Country of Publication:
- United States
- Language:
- English
Web of Science
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