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Results of the Swedish spent fuel measurement field trials with the Differential Die-Away Self-Interrogation Instrument

Trahan, Alexis C. (author)
Los Alamos Natl Lab, Los Alamos, NM 87545 USA
McMath, Garrett E. (author)
Los Alamos Natl Lab, Los Alamos, NM 87545 USA
Mendoza, Paul M. (author)
Los Alamos Natl Lab, Los Alamos, NM 87545 USA
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Trellue, Holly R. (author)
Los Alamos Natl Lab, Los Alamos, NM 87545 USA
Bäckström, Ulrika (author)
Swedish Nucl Fuel & Waste Management Co, SKB, Stockholm, Sweden
Caldeira Balkeståhl, Li (author)
Uppsala universitet,Tillämpad kärnfysik
Grape, Sophie, 1982- (author)
Uppsala universitet,Tillämpad kärnfysik
Henzl, Vlad (author)
Los Alamos Natl Lab, Los Alamos, NM 87545 USA
Leyba, Daniel (author)
Los Alamos Natl Lab, Los Alamos, NM 87545 USA
Root, Margaret A. (author)
Los Alamos Natl Lab, Los Alamos, NM 87545 USA
Sjöland, Anders (author)
Swedish Nucl Fuel & Waste Management Co, SKB, Stockholm, Sweden
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 (creator_code:org_t)
ELSEVIER, 2020
2020
English.
In: Nuclear Instruments and Methods in Physics Research Section A. - : ELSEVIER. - 0168-9002 .- 1872-9576. ; 955
  • Journal article (peer-reviewed)
Abstract Subject headings
Close  
  • Differential Die-Away Self-Interrogation (DDSI) is a method by which the characteristic die-away of neutrons from spontaneous and induced fissions is used to characterize a spent nuclear fuel assembly. A nondestructive assay (NDA) instrument was built at Los Alamos National Laboratory to implement and test the DDSI method. The DDSI instrument contains He-3 detectors which measure thermal neutrons, and the time and location of detection of each neutron is recorded via list-mode data acquisition. The instrument was sent to the Clab interim storage facility in Sweden for measurement and characterization of 50 spent pressurized water reactor (PWR) and boiling water reactor (BWR) fuel assemblies. The result was over 40 h of neutron list-mode data from a wide variety of fuel assemblies with high enough efficiency to perform neutron coincidence counting, i.e. detection of time-correlated neutrons from fission. Analysis algorithms for characterization of the fuel assemblies were tested on the Swedish spent fuel dataset. Using the measured data, multiplication, fissile mass, initial enrichment, burnup, and total plutonium mass were determined in the 50 assemblies with root mean square errors ranging from 1.5% for PWR multiplication to 11.4% for BWR fissile mass. The results in this work demonstrate that the DDSI concept is capable of characterizing spent power reactor fuel with levels of accuracy that are compatible with the requirements and objectives of various applications such as safeguards verification or facility material control and accounting.

Subject headings

NATURVETENSKAP  -- Fysik -- Subatomär fysik (hsv//swe)
NATURAL SCIENCES  -- Physical Sciences -- Subatomic Physics (hsv//eng)
TEKNIK OCH TEKNOLOGIER  -- Annan teknik -- Övrig annan teknik (hsv//swe)
ENGINEERING AND TECHNOLOGY  -- Other Engineering and Technologies -- Other Engineering and Technologies not elsewhere specified (hsv//eng)

Keyword

Differential Die-Away Self-Interrogation
Safeguards
Repository safeguards
Spent fuel
Neutron detection
Nondestructive assay

Publication and Content Type

ref (subject category)
art (subject category)

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