Determining burnup, cooling time and operational history of VVER-440 spent fuel assemblies based on in-situ gamma spectrometry at Paks Nuclear Power Plant

被引：7

作者：

Kirchknopf, Peter ^{[1
,2
]}

Almasi, Istvan ^{[1
]}

Radocz, Gabor ^{[2
]}

Nemes, Imre ^{[3
]}

Volgyesi, Peter ^{[1
]}

Szaloki, Imre ^{[2
]}

机构：

[1] Ctr Energy Res, Nucl Secur Dept, Konkoly Thege Miklos Ut 29-33, H-1121 Budapest, Hungary

[2] Budapest Univ Technol & Econ, Inst Nucl Tech, Muegyet Rkp 9, H-1111 Budapest, Hungary

[3] MVM Paks Nucl Power Plant Ltd, Reactor Phys Sect, H-7031 Paks, Hungary

来源：

ANNALS OF NUCLEAR ENERGY | 2022年 / 170卷

关键词：

Gamma spectrometry; Spent fuel; Burnup; Power history; VVER-440; NONDESTRUCTIVE ASSAY;

D O I：

10.1016/j.anucene.2022.108975

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Non-destructive assay of spent nuclear fuel assemblies using high-resolution gamma spectrometry has been developed to improve the in-situ measuring technique and the complete analytical procedure to support nuclear safeguards verification and nuclear forensics investigations. A total of 119 VVER-440 type spent fuel assemblies having individual operating histories were measured by gamma spectrometry and the activity ratios of various radionuclides were determined. The energy dependence of the detection efficiency of gamma radiation and the activities of fission products were determined by an internal calibration method. Empirical relationship between activity ratios of radionuclides, Cs-137, Cs-134, Eu-154, Ce-144, Ru-106, and Ag-110m and some main fuel parameters, such as burnup, cooling time and operational history, were calculated by regression and cluster analysis. Good empirical correlation was found between the burnup and the Cs-134(2)/((RuCs)-Ru-106-Cs-137) activity ratio, yielding burnup predictions with average deviation of 5.3% and 5.8% if the cooling time is known and unknown, respectively. The cooling time could be determined within 13.3% average deviation by using the Ag-110m/Cs-134 activity ratio. Results of the cluster analysis of the measured data indicate a deterministic relationship between the linear combinations of the Cs-134/Cs-137, Eu-154/Cs-137, Ce-144/Cs-137, and106Ru/137Cs activity ratios and the operational history of the fuel assemblies. (C)& nbsp;2022 The Author(s). Published by Elsevier Ltd.

引用

页数：9

共 4 条

[1] Simulation of the behavior of fuel elements in a VVER-440 for high burnup (using reactor no 3 of the Kol'skaya Nuclear Power Plant as an example)
Shcheglov, AS
Proselkov, VN
Smirnov, AV
Smirnov, VP
Ananev, YA
Tsibulya, VA
Kolosovskii, VG
Panin, VN
Pytkin, YN
ATOMIC ENERGY, 1996, 81 (04) : 695 - 701
[2] Simulation of the Behavior of Fuel Elements in a VVER-440 for High Burnup (Using Reactor No. 3 of the Kol'skaya Nuclear Power Plant as an Example)
Shcheglov, A. S.
Proselkov, V. N.
Smirnov, A. V.
Smirnov, V. P.
Atomic Energy, 81 (04):
[3] Enhanced formula-based method to estimate burnup, initial enrichment, and cooling time using limited gamma-ray source data of reference PWR spent nuclear fuel assemblies
Lee, Sang Hyeok
Cheong, Jae Hak
NUCLEAR ENGINEERING AND TECHNOLOGY, 2025, 57 (02)
[4] 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
Favalli, A.
Vo, D.
Grogan, B.
Jansson, P.
Liljenfeldt, H.
Mozin, V.
Schwalbach, P.
Sjoland, A.
Tobin, S. J.
Trellue, H.
Vaccaro, S.
NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, 2016, 820 : 102 - 111

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