Determining initial enrichment, burnup, and cooling time of pressurized-water-reactor spent fuel assemblies by analyzing passive gamma spectra measured at the Clab interim-fuel storage facility in Sweden

被引：36

作者：

Favalli, A. ^{[1
]}

Vo, D. ^{[1
]}

Grogan, B.

Jansson, P. ^{[3
]}

Liljenfeldt, H. ^{[5
]}

Mozin, V. ^{[6
]}

Schwalbach, P. ^{[4
]}

Sjoland, A. ^{[2
]}

Tobin, S. J. ^{[1
]}

Trellue, H. ^{[1
]}

Vaccaro, S. ^{[4
]}

机构：

[1] Los Alamos Natl Lab, Los Alamos, NM USA

[2] Swedish Nucl Fuel & Waste Management Co, Stockholm, Sweden

[3] Uppsala Univ, Uppsala, Sweden

[4] Euratom Safeguards Luxemburg, European Commiss, DG Energy, Luxembourg, Luxembourg

[5] Oak Ridge Natl Lab, Oak Ridge, TN USA

[6] Lawrence Livermore Natl Lab, Livermore, CA USA

来源：

NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT | 2016年 / 820卷

关键词：

Passive gamma; Initial enrichment; Burnup; Cooling time; Nondestructive assay of spent fuel; Germanium detector; LaBr3; detector;

D O I：

10.1016/j.nima.2016.02.072

中图分类号：

TH7 [仪器、仪表];

学科分类号：

0804 ; 080401 ; 081102 ;

摘要：

The purpose of the Next Generation Safeguards Initiative (NGSI)-Spent Fuel (SF) project is to strengthen the technical toolkit of safeguards inspectors and/or other interested parties. The NGSI-SF team is working to achieve the following technical goals more easily and efficiently than in the past using nondestructive assay measurements of spent fuel assemblies: (1) verify the initial enrichment, burnup, and cooling time of facility declaration; (2) detect the diversion or replacement of pins; (3) estimate the plutonium mass [which is also a function of the variables in (1)1; (4) estimate the decay heat; and (5) determine the reactivity of spent fuel assemblies. Since August 2013, a set of measurement campaigns has been conducted at the Central Interim Storage Facility for Spent Nuclear Fuel (Clab), in collaboration with Swedish Nuclear Fuel and Waste Management Company (SKB). One purpose of the measurement campaigns was to acquire passive gamma spectra with high -purity germanium and lanthanum bromide scintillation detectors from Pressurized Water Reactor and Boiling Water Reactor spent fuel assemblies. The absolute Cs-137 count rate and the E-154/Cs-137, Cs-134/Cs-137, Ru-106/Cs-137, and Ce-144/Cs-137 isotopic ratios were extracted; these values were used to construct corresponding model functions (which describe each measured quantity's behavior over various combinations of burnup, cooling time, and initial enrichment) and then were used to determine those same quantities in each measured spent fuel assembly. The results obtained in comparison with the operator declared values, as well as the methodology developed, are discussed in detail in the paper. (C) 2016 Published by Elsevier B.V.

引用

页码：102 / 111

页数：10