Development of INSPCT-S for inspection of spent fuel pool

William J. Walters, Alireza Haghighat, Shivakumar Sitaraman, Young Ham

Research output: Chapter in Book/Report/Conference proceedingConference contribution

7 Scopus citations

Abstract

In this paper, we discuss an accurate and fast software tool (INSPCT-S, Inspection of Nuclear Spent fuel-Pool Calculation Tool, version Spreadsheet) developed for calculation of the response of fission chambers placed in a spent fuel pool, such as Atucha-I. INSPCT-S is developed for identification of suspicious regions of the pool that may have missing or substitute assemblies. INSPCT-S uses a hybrid algorithm based on the adjoint function methodology. The neutron source is comprised of spontaneous fission, (α, n) interactions, and subcritical multiplication. The former is evaluated using the ORIGEN-ARP code, and the latter is obtained with the fission matrix (FM) formulation. The FM coefficients are determined using the MCNP Monte Carlo code, and the importance function is determined using the PENTRAN 3-D parallel Sn code. Three databases for the neutron source, FM elements, and adjoint flux are prepared as functions of different parameters including burnup, cooling time, enrichment, and pool lattice size. INSPCT-S uses the aforementioned databases and systems of equations to calculate detector responses, which are subsequently compared with normalized experimental data.

Original languageEnglish (US)
Title of host publicationReactor Dosimetry
Subtitle of host publication14th International Symposium
PublisherASTM International
Pages690-705
Number of pages16
ISBN (Print)9780803175365
DOIs
StatePublished - Jan 1 2012
Event14th International Symposium on Reactor Dosimetry - Bretton Woods, NH, United States
Duration: May 22 2011May 27 2011

Publication series

NameASTM Special Technical Publication
Volume1550 STP
ISSN (Print)0066-0558

Other

Other14th International Symposium on Reactor Dosimetry
CountryUnited States
CityBretton Woods, NH
Period5/22/115/27/11

All Science Journal Classification (ASJC) codes

  • Materials Science(all)

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