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Title: Evaluation of the concrete shield compositions from the 2010 criticality accident alarm system benchmark experiments at the CEA Valduc SILENE facility

In October 2010, a series of benchmark experiments were conducted at the French Commissariat a l'Energie Atomique et aux Energies Alternatives (CEA) Valduc SILENE facility. These experiments were a joint effort between the United States Department of Energy Nuclear Criticality Safety Program and the CEA. The purpose of these experiments was to create three benchmarks for the verification and validation of radiation transport codes and evaluated nuclear data used in the analysis of criticality accident alarm systems. This series of experiments consisted of three single-pulsed experiments with the SILENE reactor. For the first experiment, the reactor was bare (unshielded), whereas in the second and third experiments, it was shielded by lead and polyethylene, respectively. The polyethylene shield of the third experiment had a cadmium liner on its internal and external surfaces, which vertically was located near the fuel region of SILENE. During each experiment, several neutron activation foils and thermoluminescent dosimeters (TLDs) were placed around the reactor. Nearly half of the foils and TLDs had additional high-density magnetite concrete, high-density barite concrete, standard concrete, and/or BoroBond shields. CEA Saclay provided all the concrete, and the US Y-12 National Security Complex provided the BoroBond. Measurement data from the experiments were publishedmore » at the 2011 International Conference on Nuclear Criticality (ICNC 2011) and the 2013 Nuclear Criticality Safety Division (NCSD 2013) topical meeting. Preliminary computational results for the first experiment were presented in the ICNC 2011 paper, which showed poor agreement between the computational results and the measured values of the foils shielded by concrete. Recently the hydrogen content, boron content, and density of these concrete shields were further investigated within the constraints of the previously available data. New computational results for the first experiment are now available that show much better agreement with the measured values.« less
Authors:
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  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  2. French Atomic Energy Commission (CEA), Centre de Valduc, Is-sur-Tille (France)
  3. French Atomic Energy Commission (CEA), Centre de Saclay, Gif sur Yvette (France)
  4. Babcock International Group (United Kingdom)
  5. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  6. Y-12 National Security Complex, Oak Ridge, TN (United States)
Publication Date:
OSTI Identifier:
1215597
DOE Contract Number:
AC05-00OR22725
Resource Type:
Conference
Resource Relation:
Conference: ICNC 2015, Charlotte, NC (United States), 13 Sep 2015
Research Org:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org:
NNSA USDOE - National Nuclear Security Administration (NNSA)
Country of Publication:
United States
Language:
English
Subject:
73 NUCLEAR PHYSICS AND RADIATION PHYSICS; 22 GENERAL STUDIES OF NUCLEAR REACTORS; CEA; CONCRETES; POLYETHYLENES; CRITICALITY; SILENE REACTOR; DENSITY; SHIELDING; THERMOLUMINESCENT DOSEMETERS; BENCHMARKS; BARITE; BORON; CADMIUM; FOILS; HYDROGEN; LEAD; MAGNETITE; EVALUATION; SAFETY; VALIDATION; RADIATION TRANSPORT; COMPUTER CODES; COMPUTER CALCULATIONS; LINERS; PULSES; VERIFICATION; ACTIVATION DETECTORS; NUCLEAR DATA COLLECTIONS; CHEMICAL COMPOSITION CAAS; Shielding benchmark; Neutron Activation; Photon dose