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Safety analysis calculations for research and test reactors

Abstract

The goal of the RERTR (Reduced Enrichment in Research and Test Reactor) Program at ANL is to provide technical means for conversion of research and test reactors from HEU (High-Enrichment Uranium) to LEU (Low-Enrichment Uranium) fuels. In exploring the feasibility of conversion, safety considerations are a prime concern; therefore, safety analyses must be performed for reactors undergoing the conversion. This requires thorough knowledge of the important safety parameters for different types of reactors for both HEU and LEU fuel. Appropriate computer codes are needed to predict transient reactor behavior under postulated accident conditions. In this discussion, safety issues for the two general types of reactors i.e., the plate-type (MTR-type) reactor and the rod-type (TRIGA-type) reactor, resulting from the changes associated with LEU vs. HEU fuels, are explored. The plate-type fuels are typically uranium aluminide (UAl{sub x}) compounds dispersed in aluminum and clad with aluminum. Moderation is provided by the water coolant. Self shut-down reactivity coefficients with EU fuel are entirely a result of coolant heating, whereas with LEU fuel there is an additional shut down contribution provided by the direct heating of the fuel due to the Doppler coefficient. In contrast, the rod-type (TRIGA) fuels are mixtures of zirconium hydride,  More>>
Authors:
Chen, S Y; MacDonald, R; MacFarlane, D [1] 
  1. Argonne National Laboratory, Argonne, IL (United States)
Publication Date:
Aug 01, 1983
Product Type:
Conference
Report Number:
ANL/RERTR/TM-3; CONF-801144; INIS-XA-C-021
Resource Relation:
Conference: International meeting on development, fabrication, and application of Reduced Enrichment fuels for Research and Test Reactors (RERTR), Argonne, IL (United States), 12-14 Nov 1980; Other Information: 8 refs, 27 figs, 3 tabs; PBD: Aug 1983; Related Information: In: Proceedings of the international meeting on development, fabrication, and application of Reduced Enrichment fuels for Research and Test Reactors (RERTR). Base technology, 671 pages.
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; ALUMINIUM COMPOUNDS; COMPUTER CODES; DOPPLER BROADENING; ERBIUM; FUEL RODS; HEAT TRANSFER; HIGHLY ENRICHED URANIUM; INCOLOY ALLOYS; MTR REACTOR; REACTOR KINETICS; SAFETY ANALYSIS; SLIGHTLY ENRICHED URANIUM; SPECTRAL HARDENING; STAINLESS STEELS; TRIGA TYPE REACTORS; URANIUM 238; URANIUM COMPOUNDS; ZIRCONIUM HYDRIDES
Sponsoring Organizations:
U.S. Department of Energy, Assistant Secretary for Nuclear Energy, Office of Spent Fuel Management and Reprocessing Systems (United States)
OSTI ID:
20571729
Research Organizations:
Argonne National Laboratory, Argonne, IL (United States)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
TRN: XA04C1564023736
Availability:
Available from INIS in electronic form
Submitting Site:
INIS
Size:
page(s) 345-387
Announcement Date:
Mar 20, 2005

Citation Formats

Chen, S Y, MacDonald, R, and MacFarlane, D. Safety analysis calculations for research and test reactors. IAEA: N. p., 1983. Web.
Chen, S Y, MacDonald, R, & MacFarlane, D. Safety analysis calculations for research and test reactors. IAEA.
Chen, S Y, MacDonald, R, and MacFarlane, D. 1983. "Safety analysis calculations for research and test reactors." IAEA.
@misc{etde_20571729,
title = {Safety analysis calculations for research and test reactors}
author = {Chen, S Y, MacDonald, R, and MacFarlane, D}
abstractNote = {The goal of the RERTR (Reduced Enrichment in Research and Test Reactor) Program at ANL is to provide technical means for conversion of research and test reactors from HEU (High-Enrichment Uranium) to LEU (Low-Enrichment Uranium) fuels. In exploring the feasibility of conversion, safety considerations are a prime concern; therefore, safety analyses must be performed for reactors undergoing the conversion. This requires thorough knowledge of the important safety parameters for different types of reactors for both HEU and LEU fuel. Appropriate computer codes are needed to predict transient reactor behavior under postulated accident conditions. In this discussion, safety issues for the two general types of reactors i.e., the plate-type (MTR-type) reactor and the rod-type (TRIGA-type) reactor, resulting from the changes associated with LEU vs. HEU fuels, are explored. The plate-type fuels are typically uranium aluminide (UAl{sub x}) compounds dispersed in aluminum and clad with aluminum. Moderation is provided by the water coolant. Self shut-down reactivity coefficients with EU fuel are entirely a result of coolant heating, whereas with LEU fuel there is an additional shut down contribution provided by the direct heating of the fuel due to the Doppler coefficient. In contrast, the rod-type (TRIGA) fuels are mixtures of zirconium hydride, uranium, and erbium. This fuel mixture is formed into rods ( {approx} 1 cm diameter) and clad with stainless steel or Incoloy. In the TRIGA fuel the self-shutdown reactivity is more complex, depending on heating of the fuel rather than the coolant. The two most important mechanisms in providing this feedback are: spectral hardening due to neutron interaction with the ZrH moderator as it is heated and Doppler broadening of resonances in erbium and U-238. Since these phenomena result directly from heating of the fuel, and do not depend on heat transfer to the moderator/coolant, the coefficients are prompt acting. Results of transient calculations performed with existing computer codes, most suited for each type of reactor, are presented.}
place = {IAEA}
year = {1983}
month = {Aug}
}