Irradiation and measurement devices and methods development for LSNAA applications at the TRIGA-ACPR core
A Large Sample Neutron Activation Analysis (LSNAA) facility has been developed at the TRIGA-Annular Core Pulsed Reactor (ACPR) operated by the Institute for Nuclear Research in Pitesti. The central irradiation cavity of ACPR can accommodate a large irradiation device. The ACPR neutron flux characteristics are well known and spectrum adjustment techniques have been successfully applied to enhance the thermal component of the neutron flux in the central irradiation cavity. An analysis methodology was developed by employing the MCNP (a general Monte Carlo N-particle transport code) code in order to estimate counting efficiency and correction factors for the major perturbing phenomena. The paper presents the development of the experimental device, the results of the neutron flux-spectrum characterization, and preliminary steps to validate the analysis methodology.
KeywordsNeutron Activation Large sample Flux-spectrum
The work presented in this paper was performed in the frame of the International Atomic Energy Agency Coordinated Research Project “Large Sample Neutron Activation Analysis Techniques for Inhomogeneous Bulk Archaeological Samples and Large Objects”. We express our gratitude for the International Atomic Energy Agency financial support and greatly appreciate the useful and high quality technical supervision offered during the Project.
- 1.Bode P (2008) Activation analysis of large samples. In: Meyers RM (ed) Encyclopedia of analytical chemistry. Wiley, Hoboken, pp 2–21Google Scholar
- 2.MCNP—A general Monte Carlo N-particle transport code, version 5. RSICC Computer Code Collection, CCC700, Revised 10/03/2005Google Scholar
- 3.Grenwood RC, Helmer RC, Rogers JW, Dudey ND, Popek RJ, Kelloog LS, Zimmer WH (1975) Nonfission reaction rate measurements. Nucl Technol 25:274–287Google Scholar
- 4.Ikou Kondo—SELFS (1974) A program for determining self-shielding corrections for foil detectors. Report RCN 74-105, PettenGoogle Scholar
- 5.McElroy WN, Berg S (1967) Spectrum analysis by neutron detectors II and associated codes, vol II. Technical Report, AFWL-TR-67-41Google Scholar
- 6.The International Reactor Dosimetry File: IRDF-2002. www.nndc.bnl.gov/nndcscr/libraries/irdf/
- 7.Evaluated Nuclear Data File (ENDF), National Nuclear Data Center, Brookhaven National Laboratory. www.nndc.bnl.gov/exfor/endf00.jsp
- 8.Gugiu D, Roth C, Ghinescu A (2011) Counting efficiency computation for LSNAA applications, 13th international conference on modern trends in activation analysis—MTAA13. A&M University, TexasGoogle Scholar
- 9.M. Gligor – Alba Iulia – Lumea Noua Neolithic and Eneolithic Settlement in the Light of Recent Research, Ed. Mega Cluj-Napoca, 2009, ISBN: 978-606-543-045-7Google Scholar