Comparison of the Effect of Nuclear Data Uncertainty on the Accuracy of Prediction of the Isotope Composition for UO2 and MOX Fuel in Burnup Calculations for a PWR Cell

被引：0

作者：

Pisarev, A. N. ^{[1
]}

Kolesov, V. V. ^{[1
]}

机构：

[1] Natl Res Ctr, Kurchatov Inst, Moscow 123182, Russia

来源：

PHYSICS OF ATOMIC NUCLEI | 2023年 / 86卷 / 08期

关键词：

rms deviations of nuclear concentrations of nuclides; fuel burnup; nuclear data uncertainties; PROPAGATION;

D O I：

10.1134/S1063778823080136

中图分类号：

O57 [原子核物理学、高能物理学];

学科分类号：

070202 ;

摘要：

The uncertainty of quantification of nuclide density is estimated in the calculations of the burnup of UO2 and MOX fuel in the PWR cell due to the error in the neutron flux and uncertainties in the cross sections from the JEFF-3.3 library. It is shown that there is a difference between the constant components of the error for the indicated types of fuel. This difference decreases with increasing fuel burnup depth.

引用

页码：1804 / 1811

页数：8

共 8 条

[1] Comparison of the Effect of Nuclear Data Uncertainty on the Accuracy of Prediction of the Isotope Composition for UO2 and MOX Fuel in Burnup Calculations for a PWR Cell
A. N. Pisarev
V. V. Kolesov
Physics of Atomic Nuclei, 2023, 86 : 1804 - 1811
[2] UO2 versus MOX: Propagated nuclear data uncertainty for k eff, with burnup
1600, American Nuclear Society (177):
[3] UO2 Versus MOX: Propagated Nuclear Data Uncertainly for keff, with Burnup
Helgesson, Petter
Rochman, Dimitri
Sjostrand, Henrik
Alhassan, Erwin
Koning, Arjan
NUCLEAR SCIENCE AND ENGINEERING, 2014, 177 (03) : 321 - 336
[4] EFFECTS OF NUCLEAR DATA UNCERTAINTIES ON THE NEA/OECD PWR MOX/UO2 CORE ROD EJECTION BENCHMARK
Pasichnyk, Ihor
Klein, Markus
Velkov, Kiril
Zwermann, Winfried
Pautz, Andreas
NUCLEAR TECHNOLOGY, 2013, 183 (03) : 464 - 472
[5] Uncertainty propagation of fission product yields to nuclide composition and decay heat for a PWR UO2 fuel assembly
Leray, O.
Fiorito, L.
Rochman, D.
Ferroukhi, H.
Stankovskiy, A.
Van den Eynde, G.
PROGRESS IN NUCLEAR ENERGY, 2017, 101 : 486 - 495
[6] Estimation of influence of implicit effect due to multi-group cross-section perturbations on uncertainty analysis in PWR-UO2 and -MOX lattice calculations
Fujita, Tatsuya
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2025,
[7] EFFECT OF CROSS-SECTIONS DATA ON CALCULATED STATIC NEUTRONIC PARAMETERS OF PWR MOX/UO2 CORE TRANSIENT BENCHMARK CASE USING NODAL3 CODE
Luthfi, Wahid
Pinem, Surian
ACTA POLYTECHNICA, 2023, 63 (04) : 242 - 249
[8] Instant release fraction and matrix release of high burn-up UO2 spent nuclear fuel: Effect of high burn-up structure and leaching solution composition
Serrano-Purroya, D.
Clarens, F.
Gonzalez-Robles, E.
Glatz, J. P.
Wegen, D. H.
de Pablo, J.
Casas, I.
Gimenez, J.
Martinez-Esparza, A.
JOURNAL OF NUCLEAR MATERIALS, 2012, 427 (1-3) : 249 - 258

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