The possibility to probe new physics scenarios of light Majorana neutrino exchange and right-handed currents at the planned next generation neutrinoless double β decay experiment SuperNEMO is discussed. Its ability to study different isotopes and track the outgoing electrons provides the means to discriminate different underlying mechanisms for the neutrinoless double β decay by measuring the decay half-life and the electron angular and energy distributions.a
Idaho National Laboratory (INL) operates a mass separator that is currently producing high purity isotopes for use as internal standards for high precision isotope dilution mass spectrometry (IDMS). In 2008, INL began the revival of the vintage 1970s era instrument. Advancements thus far include the successful upgrading and development of system components such as the vacuum system, power supplies, ion-producing components, and beam detection equipment. Progress has been made in the separation and collection of isotopic species including those of Ar, Kr, Xe, Sr, and Ba. Particular focuses on ion source improvements and developments have proven successful with demonstrated output beam currents of over 10 lA 138 Ba and 350 nA 134 Ba from a natural abundance Ba source charge (*2.4 % 134 Ba). In order to increase production and collection of relatively high quantities (mg levels) of pure isotopes, several improvements have been made in ion source designs, source material introduction, and ion detection and collection. These improvements have produced isotopes of high purity ([98 %) and in quantities in the tens of micrograms per run. The instrument and results for pure isotope production for IDMS standards will be presented.
We have constructed a GEANT4-based detailed software model of photon transport in plastic scintillator blocks and have used it to study the NEMO-3 and SuperNEMO calorimeters employed in experiments designed to search for neutrinoless double beta decay. We compare our simulations to measurements using conversion electrons from a calibration source of 207Bi and show that the agreement is improved if wavelength-dependent properties of the calorimeter are taken into account. In this article, we briefly describe our modeling approach and results of our studies
Isotope dilution mass spectrometry (IDMS) is an analytical technique capable of providing accurate and precise quantitation of trace isotope abundance and assay providing measurement uncertainties below 1 %. To achieve these low uncertainties, the IDMS method ideally utilizes chemically pure ''spike'' solutions that consist of a single highly enriched isotope that is well-characterized relating to the abundance of companion isotopes and concentration in solution. To address a current demand for accurate 137 Cs/ 137 Ba ratio measurements for ''age'' determination of radioactive 137 Cs sources, Idaho National Laboratory (INL) is producing enriched 134 Ba isotopes that are tobe used for IDMS spikes to accurately determine 137 Ba accumulation from the decay of 137 Cs. The final objective of this work it to provide a homogenous set of reference materials that the National Institute of Standards and Technology can certify as standard reference materials used for IDMS. The process that was developed at INL for the separation and isolation of Ba isotopes, chemical purification of the isotopes in solution, and the encapsulation of the materials will be described.
Current
state-of-the-art fission product separations frequently
involve multiple independent separation columns and sample manipulation
processes; to couple these processes together, multiple evaporation
and transposition steps are often required. The addition of these
steps results in lengthy separation times, increased analysis costs,
the potential for sample loss, and release of radioactive contamination.
We report a new semiautomated method for the rapid separation of U,
Zr, Mo, Ba, Sr, Te, and lanthanide fission products from irradiated
uranium samples. Chemical yields for U, Zr, Ba, Sr, Te and the lanthanides
from less than 3-day old uranium fission product samples are consistently
greater than 90%, while those of Mo are greater than 70%. This method
minimizes the use and addition of oxidation and reduction reagents
that often cause issues with retention and separation. Uranium dissolution
and fission product separations using this single-pass method are
achievable in under 2 h, representing a significant improvement over
traditional gravimetric uranium fission product separation procedures.
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