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Title: Evaluation of the Use of Existing RELAP5-3D Models to Represent the Actinide Burner Test Reactor

Abstract

The RELAP5-3D code is being considered as a thermal-hydraulic system code to support the development of the sodium-cooled Actinide Burner Test Reactor as part of Global Nuclear Energy Partnership. An evaluation was performed to determine whether the control system could be used to simulate the effects of non-convective mechanisms of heat transport in the fluid that are not currently represented with internal code models, including axial and radial heat conduction in the fluid and subchannel mixing. The evaluation also determined the relative importance of axial and radial heat conduction and fluid mixing on peak cladding temperature for a wide range of steady conditions and during a representative loss-of-flow transient. The evaluation was performed using a RELAP5-3D model of a subassembly in the Experimental Breeder Reactor-II, which was used as a surrogate for the Actinide Burner Test Reactor. An evaluation was also performed to determine if the existing centrifugal pump model could be used to simulate the performance of electromagnetic pumps.

Authors:
Publication Date:
Research Org.:
Idaho National Laboratory (INL)
Sponsoring Org.:
DOE - NE
OSTI Identifier:
911901
Report Number(s):
INL/EXT-07-12228
TRN: US0800202
DOE Contract Number:
DE-AC07-99ID-13727
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
21 - SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS, 22 - GENERAL STUDIES OF NUCLEAR REACTORS; ACTINIDES; BURNERS; CENTRIFUGAL PUMPS; CONTROL SYSTEMS; ELECTROMAGNETIC PUMPS; EVALUATION; LOSS OF FLOW; NUCLEAR ENERGY; PERFORMANCE; TEST REACTORS; TRANSPORT; ABTR; Electromagnetic pumps; Heat conduction; Mixing; RELAP5-3D; Sodium

Citation Formats

C. B. Davis. Evaluation of the Use of Existing RELAP5-3D Models to Represent the Actinide Burner Test Reactor. United States: N. p., 2007. Web. doi:10.2172/911901.
C. B. Davis. Evaluation of the Use of Existing RELAP5-3D Models to Represent the Actinide Burner Test Reactor. United States. doi:10.2172/911901.
C. B. Davis. Thu . "Evaluation of the Use of Existing RELAP5-3D Models to Represent the Actinide Burner Test Reactor". United States. doi:10.2172/911901. https://www.osti.gov/servlets/purl/911901.
@article{osti_911901,
title = {Evaluation of the Use of Existing RELAP5-3D Models to Represent the Actinide Burner Test Reactor},
author = {C. B. Davis},
abstractNote = {The RELAP5-3D code is being considered as a thermal-hydraulic system code to support the development of the sodium-cooled Actinide Burner Test Reactor as part of Global Nuclear Energy Partnership. An evaluation was performed to determine whether the control system could be used to simulate the effects of non-convective mechanisms of heat transport in the fluid that are not currently represented with internal code models, including axial and radial heat conduction in the fluid and subchannel mixing. The evaluation also determined the relative importance of axial and radial heat conduction and fluid mixing on peak cladding temperature for a wide range of steady conditions and during a representative loss-of-flow transient. The evaluation was performed using a RELAP5-3D model of a subassembly in the Experimental Breeder Reactor-II, which was used as a surrogate for the Actinide Burner Test Reactor. An evaluation was also performed to determine if the existing centrifugal pump model could be used to simulate the performance of electromagnetic pumps.},
doi = {10.2172/911901},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Feb 01 00:00:00 EST 2007},
month = {Thu Feb 01 00:00:00 EST 2007}
}

Technical Report:

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  • The Actinide Burner Test Reactor (ABTR) is envisioned as a sodium-cooled, fast reactor that will burn the actinides generated in light water reactors to reduce nuclear waste and ease proliferation concerns. The RELAP5-3D computer code is being considered as the thermal-hydraulic system code to support the development of the ABTR. An evaluation was performed to determine the applicability of RELAP5-3D for the analysis of a sodium-cooled fast reactor. The applicability evaluation consisted of several steps, including identifying the important transients and phenomena expected in the ABTR, identifying the models and correlations that affect the code’s calculation of the important phenomena,more » and evaluating the applicability of the important models and correlations for calculating the important phenomena expected in the ABTR. The applicability evaluation identified code improvements and additional models needed to simulate the ABTR. The accuracy of the calculated thermodynamic and transport properties for sodium was also evaluated.« less
  • The final, corrected field-test data for the Pricetown I underground coal gasification project are averaged into five phases containing 63 stages. The resulting data are used to determine probable affected geometries of the reverse combustion linking (RCL), combustion link enhancement (CLE), and forward gasification (FG) phases. After RCL, the link diameters between production/injection wells 2-3 and wells 1-2 were 2.39 ft and 2.56 ft/sup 3/, respectively. About 71% of the volatile matter in the link was removed. CLE of the porous link occurred under both sublaminar and laminar flow regimes, with a consumption of about 95% of the volatile mattermore » in the link. The CLE computer model predicts a link cross section of about 7 ft high by 32 ft wide at the injection well just prior to gasification. The extent of gasification during linking is found to be insignificant. During forward gasification, the absence of water (steam) and volatile matter near the injection region resulted in partial oxidation of the char being the major gasification reaction followed by downstream or periferal devolatilization. Based on thermocouple indications and the FG computer model cavity growth predictions, it appears that only 20% of the char reacted giving an average cavity height of 3.3 ft and maximum width of about 30 ft. Approximately 52% of the coal affected was recovered during the field test. The FG phase was apparently terminated because of the rapid temperature drop when the burden became exposed as indicated by thermocouple measurements and the FG model temperature calculations. This led to condensation and solidification of tars in the link and wells. It is imperative to maintain base temperatures by providing superheated steam and oxygen in future field tests, as well as to improve the quality of the product gas. 43 figures, 13 tables.« less
  • Models which describe momentum exchange in two-phase, vapor-liquid flows are surveyed. These models are related to the momentum exchange coefficient formulations used in the SIMMER code. The result is a set of model-dependent exchange coefficients for various flow regimes. Criteria for flow regime transitions and experimental needs in momentum exchange modeling are also discussed.
  • Results of a preliminary safety evaluation of the Advanced Burner Test Reactor (ABTR) pre-conceptual design are reported. The ABTR safety design approach is described. Traditional defense-in-depth design features are supplemented with passive safety performance characteristics that include natural circulation emergency decay heat removal and reactor power reduction by inherent reactivity feedbacks in accidents. ABTR safety performance in design-basis and beyond-design-basis accident sequences is estimated based on analyses. Modeling assumptions and input data for safety analyses are presented. Analysis results for simulation of simultaneous loss of coolant pumping power and normal heat rejection are presented and discussed, both for the casemore » with reactor scram and the case without reactor scram. The analysis results indicate that the ABTR pre-conceptual design is capable of undergoing bounding design-basis and beyond-design-basis accidents without fuel cladding failures. The first line of defense for protection of the public against release of radioactivity in accidents remains intact with significant margin. A comparison and evaluation of general safety design criteria for the ABTR conceptual design phase are presented in an appendix. A second appendix presents SASSYS-1 computer code capabilities and modeling enhancements implemented for ABTR analyses.« less