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Title: Demonstration of Coupled Tiamat Single Assembly Calculations

Abstract

This report corresponds to milestone L3:PHI.PCI.P15.03, which was originally intended to investigate the time discretization approaches with the newly developed fully coupled Tiamat capability, targeting single assembly problems.

Authors:
 [1];  [1];  [1];  [2];  [1];  [2];  [3];  [3];  [3];  [3]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
  2. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
  3. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1400149
Report Number(s):
ORNL/TM-2017/321
75551
DOE Contract Number:
AC05-00OR22725
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
97 MATHEMATICS AND COMPUTING

Citation Formats

Novascone, Stephen R., Hales, Jason D., Gardner, Russell, Pawlowski, R. P. P., Pastore, Giovanni, Toth, Alex, Clarno, Kevin T., Collins, Benjamin S., Stimpson, Shane G., and Powers, Jeffrey J.. Demonstration of Coupled Tiamat Single Assembly Calculations. United States: N. p., 2017. Web. doi:10.2172/1400149.
Novascone, Stephen R., Hales, Jason D., Gardner, Russell, Pawlowski, R. P. P., Pastore, Giovanni, Toth, Alex, Clarno, Kevin T., Collins, Benjamin S., Stimpson, Shane G., & Powers, Jeffrey J.. Demonstration of Coupled Tiamat Single Assembly Calculations. United States. doi:10.2172/1400149.
Novascone, Stephen R., Hales, Jason D., Gardner, Russell, Pawlowski, R. P. P., Pastore, Giovanni, Toth, Alex, Clarno, Kevin T., Collins, Benjamin S., Stimpson, Shane G., and Powers, Jeffrey J.. Thu . "Demonstration of Coupled Tiamat Single Assembly Calculations". United States. doi:10.2172/1400149. https://www.osti.gov/servlets/purl/1400149.
@article{osti_1400149,
title = {Demonstration of Coupled Tiamat Single Assembly Calculations},
author = {Novascone, Stephen R. and Hales, Jason D. and Gardner, Russell and Pawlowski, R. P. P. and Pastore, Giovanni and Toth, Alex and Clarno, Kevin T. and Collins, Benjamin S. and Stimpson, Shane G. and Powers, Jeffrey J.},
abstractNote = {This report corresponds to milestone L3:PHI.PCI.P15.03, which was originally intended to investigate the time discretization approaches with the newly developed fully coupled Tiamat capability, targeting single assembly problems.},
doi = {10.2172/1400149},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Jun 01 00:00:00 EDT 2017},
month = {Thu Jun 01 00:00:00 EDT 2017}
}

Technical Report:

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  • The inductively coupled plasma/atomic emission spectroscopy [ICP/AES (ICP)] system for elemental analyses in support of vitrification processing was first installed in 1986. The initial instrument was a Jobin Yvon (JY) Model JY-70 ICP that consisted of sequential and simultaneous spectrometers for analysis of nonradioactive samples as radioactive surrogates. The JY-70 ICP continued supporting nonradioactive testing during the Functional and Checkout Testing of Systems (FACTS) using the full-scale melter with ``cold'' (nonradioactive) testing campaigns. As a result, the need for another system was identified to allow for the analysis of radioactive samples. The Mass Spec (Spectrometry) Lab was established for themore » installation of the modified ICP system for handling radioactive samples. The conceptual setup of another ICP was predicated on the use of a hood to allow ease of accessibility of the torch, nebulizer, and spray chamber, and the minimization of air flow paths. However, reconsideration of the radioactive sample dose rate and contamination levels led to the configuration of the glovebox system with a common transfer interface box for the ICP and the inductively coupled plasma-mass spectrometer (ICP-MS) glovebox assemblies. As a result, a simultaneous Model JY-50P ICP with glovebox was installed in 1990 as a first generation ICP glovebox system. This was one of the first ICP glovebox assemblies connected with an ICP-MS glovebox system. Since the economics of processing high-level radioactive waste (HLW) required the availability of an instrument to operate 24 hours a day throughout the year without any downtime, a second generation ICP glovebox assembly was designed, manufactured, and installed in 1995 using a Model JY-46P ICP. These two ICP glovebox systems continue to support vitrification of the HLW into canisters for storage. The ICP systems have been instrumental in monitoring vitrification batch processing. To date, remote sample preparation and compositional analysis of key parameters, i.e., greater than 0.5% weight percent metal oxides, during batch processing (waste initials, glass formers, waste plus glass formers, and glass) has verified the composition to be within the acceptance criteria and generated the necessary data for the Waste Qualification Report.« less
  • Consolidation of spent fuel is under active consideration as the US Department of Energy plans to dispose of spent fuel. During consolidation, the fuel pins are removed from an intact fuel assembly and repackaged into a more compact configuration. After repackaging, approximately 30 kg of residual spent fuel assembly hardware per assembly remains that is also radioactive and requires disposal. Understanding the nature of this secondary waste stream is critical to designing a system that will properly handle, package, store, and dispose of the waste. This report presents a methodology for estimating the radionuclide inventory in irradiated spent fuel hardware.more » Ratios are developed that allow the use of ORIGEN2 computer code calculations to be applied to regions that are outside the fueled region. The ratios are based on the analysis of samples of irradiated hardware from spent fuel assemblies. The results of this research are presented in three volumes. In Volume 1, the development of scaling factors that can be used with ORIGEN2 calculations to estimate activation of spent fuel assembly hardware is documented. The results from laboratory analysis of irradiated spent-fuel hardware samples are also presented in Volume 1. In Volumes 2 and 3, the calculated flux profiles of spent nuclear fuel assemblies are presented for pressurized water reactors and boiling water reactors, respectively. The results presented in Volumes 2 and 3 were used to develop the scaling factors documented in Volume 1. 5 refs., 4 figs., 21 tabs.« less