El Messaoudi M, Chouak A, Lferde M, Cherkaoui R
Laboratoire de Physique Nucléaire, Département de Physique, Faculté des Sciences, Avenue Ibn Battouta B.P 1014, Rabat, Morocco.
Radiat Prot Dosimetry. 2004;108(3):247-53. doi: 10.1093/rpd/nch034.
This paper presents the results obtained in a comparison of three neutron spectrum unfolding procedures based on the SAND, MINCHI and UNFANA computer programs. The calculations were performed with data obtained previously from measurements using the PTB Bonner sphere spectrometer and taken from the literature; the neutron dosimetry was done with the Leake rem-meter. The evaluation of some spectrum hardness quantifiers is also reported. The codes give comparable neutron spectrum results. Relative to ambient dose equivalent derived from the Bonner sphere system, as a function of the unfolding code used, the Leake calculated readings were typically 1.16 to 1.91 and 1.58 to 2.69 times larger for the environment of a transport cask with spent fuel elements (Clab) and inside the containment building of a pressurised water reactor (Ring-G), respectively, depending on the calibration fields.
本文介绍了基于SAND、MINCHI和UNFANA计算机程序对三种中子能谱展开程序进行比较所获得的结果。计算使用了先前通过PTB邦纳球谱仪测量获得并取自文献的数据；中子剂量测定采用利克rem计。还报告了对一些谱硬度量化指标的评估。这些程序给出了可比的中子能谱结果。相对于从邦纳球系统得出的环境剂量当量，根据所使用的展开程序，对于装有乏燃料元件的运输容器（Clab）环境和压水反应堆安全壳建筑物内部（Ring-G），利克计算读数分别通常比其大1.16至1.91倍和1.58至2.69倍，具体取决于校准场。
