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Title: Fiscal Year (FY) 2017 Activities for the Spent Fuel Nondestructive Assay Project

Abstract

The main focus of research in the NA-241 spent fuel nondestructive assay (NDA) project in FY17 has been completing the fabrication and testing of two prototype instruments for upcoming spent fuel measurements at the Clab interim storage facility in Sweden. One is a passive instrument: Differential Die-away Self Interrogation-Passive Neutron Albedo Reactivity (DDSI), and one is an active instrument: Differential Die-Away-Californium Interrogation with Prompt Neutron (DDA). DDSI was fabricated and tested with fresh fuel at Los Alamos National Laboratory in FY15 and FY16, then shipped to Sweden at the beginning of FY17. Research was performed in FY17 to simplify results from the data acquisition system, which is complex because signals from 56 different 3He detectors must be processed using list mode data. The DDA instrument was fabricated at the end of FY16. New high count rate electronics better suited for a spent fuel environment (i.e., KM-200 preamplifiers) were built specifically for this instrument in FY17, and new Tygon tubing to house electrical cables was purchased and installed. Fresh fuel tests using the DDA instrument with numerous configurations of fuel rods containing depleted uranium (DU), low enriched uranium (LEU), and LEU with burnable poisons (Gd) were successfully performed and compared tomore » simulations.1 Additionally, members of the spent fuel NDA project team travelled to Sweden for a “spent fuel characterization and decay heat” workshop involving simulations of spent fuel and analysis of uncertainties in decay heat calculations.« less

Authors:
 [1];  [1];  [1];  [1];  [2];  [2];  [2];  [2]
  1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
  2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Publication Date:
Research Org.:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Nonproliferation (NA-20)
OSTI Identifier:
1392821
Report Number(s):
LA-UR-17-28157
DOE Contract Number:
AC52-06NA25396
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS

Citation Formats

Trellue, Holly Renee, Trahan, Alexis Chanel, McMath, Garrett Earl, Swinhoe, Martyn Thomas, Hu, Jianwei, Worrall, Andrew, Ilas, Germina, and Grogan, Brandon. Fiscal Year (FY) 2017 Activities for the Spent Fuel Nondestructive Assay Project. United States: N. p., 2017. Web. doi:10.2172/1392821.
Trellue, Holly Renee, Trahan, Alexis Chanel, McMath, Garrett Earl, Swinhoe, Martyn Thomas, Hu, Jianwei, Worrall, Andrew, Ilas, Germina, & Grogan, Brandon. Fiscal Year (FY) 2017 Activities for the Spent Fuel Nondestructive Assay Project. United States. doi:10.2172/1392821.
Trellue, Holly Renee, Trahan, Alexis Chanel, McMath, Garrett Earl, Swinhoe, Martyn Thomas, Hu, Jianwei, Worrall, Andrew, Ilas, Germina, and Grogan, Brandon. 2017. "Fiscal Year (FY) 2017 Activities for the Spent Fuel Nondestructive Assay Project". United States. doi:10.2172/1392821. https://www.osti.gov/servlets/purl/1392821.
@article{osti_1392821,
title = {Fiscal Year (FY) 2017 Activities for the Spent Fuel Nondestructive Assay Project},
author = {Trellue, Holly Renee and Trahan, Alexis Chanel and McMath, Garrett Earl and Swinhoe, Martyn Thomas and Hu, Jianwei and Worrall, Andrew and Ilas, Germina and Grogan, Brandon},
abstractNote = {The main focus of research in the NA-241 spent fuel nondestructive assay (NDA) project in FY17 has been completing the fabrication and testing of two prototype instruments for upcoming spent fuel measurements at the Clab interim storage facility in Sweden. One is a passive instrument: Differential Die-away Self Interrogation-Passive Neutron Albedo Reactivity (DDSI), and one is an active instrument: Differential Die-Away-Californium Interrogation with Prompt Neutron (DDA). DDSI was fabricated and tested with fresh fuel at Los Alamos National Laboratory in FY15 and FY16, then shipped to Sweden at the beginning of FY17. Research was performed in FY17 to simplify results from the data acquisition system, which is complex because signals from 56 different 3He detectors must be processed using list mode data. The DDA instrument was fabricated at the end of FY16. New high count rate electronics better suited for a spent fuel environment (i.e., KM-200 preamplifiers) were built specifically for this instrument in FY17, and new Tygon tubing to house electrical cables was purchased and installed. Fresh fuel tests using the DDA instrument with numerous configurations of fuel rods containing depleted uranium (DU), low enriched uranium (LEU), and LEU with burnable poisons (Gd) were successfully performed and compared to simulations.1 Additionally, members of the spent fuel NDA project team travelled to Sweden for a “spent fuel characterization and decay heat” workshop involving simulations of spent fuel and analysis of uncertainties in decay heat calculations.},
doi = {10.2172/1392821},
journal = {},
number = ,
volume = ,
place = {United States},
year = 2017,
month = 9
}

Technical Report:

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  • This document is a revision to WHC-SD-SNF-SD-002, and is issued to support the individual projects that make up the Spent Nuclear Fuel Project in the lower-tier functions, requirements, interfaces, and technical baseline items. It presents results of engineering analyses since Sept. 1994. The mission of the SNFP on the Hanford site is to provide safety, economic, environmentally sound management of Hanford SNF in a manner that stages it to final disposition. This particularly involves K Basin fuel, although other SNF is involved also.
  • Volume 2 of this SNFP technical baseline document presents the data which supports the information contained in Volume 1 of this document, Baseline Description. This document presents the results of the SNFP systems engineering analyses since September 1994. The mission of the Spent Nuclear Fuel Project at Hanford is to provide safe, economic, and environmentally sound management of Hanford SNF in a manner that stages it to final disposition. Spent fuels include what are in the K Basins, various buildings throughout the site, and fuels from the FFTF.
  • This report summarizes an evaluation of the potential use of nondestructive assay (NDA) and nondestructive examination (NDE) technologies on DOE spent nuclear fuel (SNF). It presents the NDA/NDE information necessary for the National Spent Nuclear Fuel Program (NSNFP) and the SNF storage sites to use when defining that role, if any, of NDA/NDE in characterization and certification processes. Note that the potential role for NDA/NDE includes confirmatory testing on a sampling basis and is not restricted to use as a primary, item-specific, data collection method. The evaluation does not attempt to serve as a basis for selecting systems for developmentmore » or deployment. Information was collected on 27 systems being developed at eight DOE locations. The systems considered are developed to some degree, but are not ready for deployment on the full range of DOE SNF and still require additional development. The system development may only involve demonstrating performance on additional SNF, packaging the system for deployment, and developing calibration standards, or it may be as extensive as performing additional basic research. Development time is considered to range from one to four years. We conclude that NDA/NDE systems are capable of playing a key role in the characterization and certification of DOE SNF, either as the primary data source or as a confirmatory test. NDA/NDE systems will be able to measure seven of the nine key SNF properties and to derive data for the two key properties not measured directly. The anticipated performance goals of these key properties are considered achievable except for enrichment measurements on fuels near 20% enrichment. NDA/NDE systems can likely be developed to measure the standard canisters now being considered for co-disposal of DOE SNF. This ability would allow the preparation of DOE SNF for storage now and the characterization and certification to be finalize later.« less
  • Several methods were tested for the non-destructive assay of irradiated nuclear fuel assemblies stored in water-filled pools: burnup measurement by neutron emission; residual fissile measurement by multiplication change with boron displacement; and residual fissile measurement by neutron-source multiplication. It was found that both burnup and residual fissile content could be measured through counting neutron emission from the fuel, both with and without a neutron source. Accuracy of 770 MWD/MTU was attained in burnup determination, while residual fissile content measurements had errors of about 0.1% absolute in fissile content. Still more accurate fissile content measurements appear possible, since the statistical uncertaintiesmore » in fissile assay (neglecting systematic errors) are estimated to be 0.016% absolute in fissle content. Thus it appears to be practical to assay irradiated fuel asseemblies to high accuracy while stored in fuel-storage pools. Further development is recommended, however, to test out the practical limits of precision attainable with this procedure.« less