Design of a Prototype Differential Die‐Away Instrument Proposed for Swedish Spent Nuclear Fuel Characterization

详细信息    查看全文

• 作者：Tomas Martinik^a ; ^b ; ^{tomas.martinik@physics.uu.se" class="auth_mail" title="E-mail the corresponding author} ; Vladimir Henzl^b ; Sophie Grape^a ; Peter Jansson^a ; Martyn T. Swinhoe^b ; Alison V. Goodsell^b ; Stephen J. Tobin^a ; ^b ; ^c
• 关键词：Differential die-away ; Spent nuclear fuel ; Clab ; Non-destructive assay ; Neutron detection
• 刊名：Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment
• 出版年：2016
• 出版时间：11 June 2016
• 年：2016
• 卷：821
• 期：Complete
• 页码：55-65
• 全文大小：1397 K

文摘

As part of the United States (US) Department of Energy׳s Next Generation Safeguards Initiative Spent Fuel (NGSI-SF) project, the traditional Differential Die-Away (DDA) method that was originally developed for waste drum assay has been investigated and modified to provide a novel application to characterize or verify spent nuclear fuel (SNF). Following the promising, yet largely theoretical and simulation based, research of physics aspects of the DDA technique applied to SNF assay during the early stages of the NGSI-SF project, the most recent effort has been focused on the practical aspects of developing the first fully functional and deployable DDA prototype instrument for spent fuel. As a result of the collaboration among US research institutions and Sweden, the opportunity to test the newly proposed instrument׳s performance with commercial grade SNF at the Swedish Interim Storage Facility (Clab) emerged. Therefore the design of this instrument prototype has to accommodate the requirements of the Swedish regulator as well as specific engineering constrains given by the unique industrial environment. Within this paper, we identify key components of the DDA based instrument and we present methodology for evaluation and the results of a selection of the most relevant design parameters in order to optimize the performance for a given application, i.e. test-deployment, including assay of 50 preselected spent nuclear fuel assemblies of both pressurized (PWR) as well as boiling (BWR) water reactor type.