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Inherent accommodation of unprotected loss-of-flow accidents in LMFBRs

Description: Inherent safety is a major focus of attention in fast reactor design. Extensive efforts have been given to utilizing intrinsic characteristics of sodium-cooled reactors to enhance the plant's ability to accommodate even the most unlikely accidents, such as loss-of-flow (LOF) with failure to scram. The renewed interest in the pool concept partially reflects this new direction. The reintroduction of metal fuel also opens a new frontier for fast reactor safety technology. This study explores the potential of the metal fuel in achieving designs which are inherently safe against unprotected LOF accidents. The study is conducted using the SASSYS code and is based on an 1000 MWe pool design.
Date: January 1, 1984
Creator: Su, S.F. & Sevy, R.H.
Partner: UNT Libraries Government Documents Department

Accommodation of unprotected accidents by inherent safety design features in metallic and oxide-fueled LMFBRs

Description: This paper presents the results of a study of the effectivness of intrinsic design features to mitigate the consequences of unprotected accidents in metallic and oxide-fueled LMFBRs. The accidents analyzed belong to the class generally considered to lead to core disruption; unprotected loss-of-flow (LOF) and transient over-power (TOP). Results of the study demonstrate the potential for design features to meliorate accident consequences, and in some cases to render them benign. Emphasis is placed on the relative performance of metallic and oxide-fueled core designs.
Date: January 1, 1985
Creator: Cahalan, J.E.; Sevy, R.H. & Su, S.F.
Partner: UNT Libraries Government Documents Department

Neutron-Induced Helium Implantation in GCFR Cladding

Description: The neutron-induced implantation of helium atoms on the exterior surfaces of the cladding of a prototypic gas-cooled fast reactor (GCFR) has been investigated analytically. A flux of recoil helium particles as high as 4.2 x 10¹⁰ He/cm sq.s at the cladding surface has been calculated at the peak power location in the core of a 300-MWe GCFR. The calculated profile of the helium implantation rates indicates that although some helium is implanted as deep as 20 microns, more than 99% of helium particles are implanted in the first 2-microns -deep layer below the cladding surface. Therefore, the implanted helium particles should mainly affect surface properties of the GCFR cladding.
Date: October 1980
Creator: Yamada, H.; Poeppel, R. B. & Sevy, R. H.
Partner: UNT Libraries Government Documents Department

Inherent controllability in modular ALMRs

Description: As part of recent development efforts on advanced reactor designs ANL has proposed the IFR (Integral Fast Reactor) concept. The IFR concept is currently being applied to modular sized reactors which would be built in multiple power paks together with an integrated fuel cycle facility. It has been amply demonstrated that the concept as applied to the modular designs has significant advantages in regard to ATWS transients. Attention is now being focussed on determining whether or not those advantages deriving from the traits of the IFR can be translated to the operational/DBA (design basis accident) class of transients. 5 refs., 3 figs., 3 tabs.
Date: January 1, 1989
Creator: Sackett, J.I.; Sevy, R.H. & Wei, T.Y.C.
Partner: UNT Libraries Government Documents Department

Safety characteristics of the integral fast reactor concept

Description: The Integral Fast Reactor (IFR) concept is an innovative approach to liquid metal reactor design which is being studied by Argonne National Laboratory. Two of the key features of the IFR design are a metal fuel core design, based on the fuel technology developed at EBR-II, and an integral fuel cycle with a colocated fuel cycle facility based on the compact and simplified process steps made possible by the use of metal fuel. The paper presents the safety characteristics of the IFR concept which derive from the use of metal fuel. Liquid metal reactors, because of the low pressure coolant operating far below its boiling point, the natural circulation capability, and high system heat capacities, possess a high degree of inherent safety. The use of metallic fuel allows the reactor designer to further enhance the system capability for passive accommodation of postulated accidents.
Date: January 1, 1985
Creator: Marchaterre, J.F.; Cahalan, J.E.; Sevy, R.H. & Wright, A.E.
Partner: UNT Libraries Government Documents Department

Integral fast reactor safety features

Description: The Integral Fast Reactor (IFR) is an advanced liquid-metal-cooled reactor concept being developed at Argonne National Laboratory. The two major goals of the IFR development effort are improved economics and enhanced safety. In addition to liquid metal cooling, the principal design features that distinguish the IFR are: (1) a pool-type primary system, (2) an advanced ternary alloy metallic fuel, and (3) an integral fuel cycle with on-site fuel reprocessing and fabrication. This paper focuses on the technical aspects of the improved safety margins available in the IFR concept. This increased level of safety is made possible by (1) the liquid metal (sodium) coolant and pool-type primary system layout, which together facilitate passive decay heat removal, and (2) a sodium-bonded metallic fuel pin design with thermal and neutronic properties that provide passive core responses which control and mitigate the consequences of reactor accidents.
Date: January 1, 1988
Creator: Cahalan, J.E.; Kramer, J.M.; Marchaterre, J.F.; Mueller, C.J.; Pedersen, D.R.; Sevy, R.H. et al.
Partner: UNT Libraries Government Documents Department

A risk characterization of safety research areas for Integral Fast Reactor program planning

Description: This paper characterizes the areas of Integral Fast Reactor (IFR) safety research in terms of their importance in addressing the risk of core disruption sequences for innovative designs. Such sequences have traditionally been determined to constitute the primary risk to public health and safety. All core disruption sequences are folded into four fault categories: classic unprotected (unscrammed) events; loss of decay heat; local fault propagation; and failure of critical reactor structures. Event trees are used to describe these sequences and the areas in the IFR Safety and related Base Technology research programs are discussed with respect to their relevance in addressing the key issues in preventing or delimiting core disruptive sequences. Thus a measure of potential for risk reduction is obtained for guidance in establishing research priorites.
Date: January 1, 1988
Creator: Mueller, C.J.; Cahalan, J.E.; Hill, D.J.; Kramer, J.M.; Marchaterre, J.F.; Pedersen, D.R. et al.
Partner: UNT Libraries Government Documents Department