Determination of total plutonium content in spent nuclear fuel assemblies with the differential die-away self-interrogation instrument

Alexis C. Kaplan, Vladimir Henzl, Howard O. Menlove, Martyn T. Swinhoe, Anthony P. Belian, Marek Flaska, Sara A. Pozzi

Research output: Contribution to journalArticle

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Abstract

As a part of the Next Generation Safeguards Initiative Spent Fuel project, we simulate the response of the Differential Die-away Self-Interrogation (DDSI) instrument to determine total elemental plutonium content in an assayed spent nuclear fuel assembly (SFA). We apply recently developed concepts that relate total plutonium mass with SFA multiplication and passive neutron count rate. In this work, the multiplication of the SFA is determined from the die-away time in the early time domain of the Rossi-Alpha distributions measured directly by the DDSI instrument. We utilize MCNP to test the method against 44 pressurized water reactor SFAs from a simulated spent fuel library with a wide dynamic range of characteristic parameters such as initial enrichment, burnup, and cooling time. Under ideal conditions, discounting possible errors of a real world measurement, a root mean square agreement between true and determined total Pu mass of 2.1% is achieved.

Original languageEnglish (US)
Pages (from-to)347-351
Number of pages5
JournalNuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment
Volume764
DOIs
StatePublished - Nov 11 2014

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All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Instrumentation

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