Freshly induced short-lived gamma-ray activity as a measure of fission rates in lightly re-irradiated spent fuel

被引：9

作者：

Krohnert, H. ^{[1
]}

Perret, G. ^{[1
]}

Murphy, M. F. ^{[1
]}

Chawla, R. ^{[1
,2
]}

机构：

[1] PSI, OPRA E07, CH-5232 Villigen, Switzerland

[2] Ecole Polytech Fed Lausanne, CH-1015 Lausanne, Switzerland

来源：

NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT | 2010年 / 624卷 / 01期

关键词：

Light water reactor fuel; Spent fuel; Fission rates; Gamma ray spectrometry; Short lived fission products; MCNPX;

D O I：

10.1016/j.nima.2010.09.033

中图分类号：

TH7 [仪器、仪表];

学科分类号：

0804 ; 080401 ; 081102 ;

摘要：

A new measurement technique has been developed to determine fission rates in burnt fuel following re-irradiation in a zero-power research reactor The development has been made in the frame of the LIFE@PROTEUS program at the Paul Scherrer Institute which aims at characterizing the interfaces between fresh and highly burnt fuel assemblies in modern LWRs To discriminate against the high intrinsic gamma-ray activity of the burnt fuel the proposed measurement technique uses high-energy gamma-rays above 2000 keV emitted by short-lived fission products freshly produced in the fuel To demonstrate the feasibility of this technique a fresh UO(2) sample and a 36 GWd/t burnt UO(2) sample were irradiated in the PROTEUS reactor and their gamma-ray activities were recorded directly after irradiation For both fresh and the burnt fuel samples relative fission rates were derived for different core positions based on the short-lived (142)La (2542 keV) (89)Rb (2570 keV) (138)Cs (2640 key) and (95)Y (3576 key) gamma-ray lines Uncertainties on the inter-position fission rate ratios were mainly due to the uncertainties on the net-area of the gamma-ray peaks and were about 1-3% for the fresh sample and 3-6% for the burnt one Thus for the first time It has been shown that the short-lived gamma-ray activity induced in burnt fuel by irradiation in a zero-power reactor can be used as a quantitative measure of the fission rate For both fresh and burnt fuel the measured results agreed within the uncertainties with Monte Carlo (MCNPX) predictions (C) 2010 Elsevier B V All rights reserved

引用

页码：101 / 108

页数：8

共 11 条

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[Anonymous], 2005, HYPERLAB 2005 GAMM S

[2] Optimised non-invasive method to determine 238U-captures-to-total-fissions in reactor fuel [J].