Assessment of the FBR Core Disruptive Accident (CDA): The Role and Application of General Behavior Principles (GBPs)

General behavior principles (GBPs) first introduced in 1976 (H. K. Fauske, the Role of Core-Disruptive Accidents in Design and Licensing of LMFBRs, Nuclear Safety, Vol. 17, No. 5, 550–567, 1976) are applied to assess the core disruptive accident (CDA) outcome for a large (3,500MWt) high power density oxide-fueled sodium-cooled fast breeder reactor (FBR). Non-energetic termination in the so-called Initiating Phase is emphasized and is made possible by considering departures from the traditional core design including the Subassembly Inner Duct and Limited Blanket Removal concepts. This early accident scenario termination eliminates potential concerns raised related to recriticality events and also facilitates the potential for in-vessel fuel debris coolability for the large FBR with a compact reactor vessel.

[1]  M. Epstein,et al.  Applications of the Turbulent Entrainment Assumption to Immiscible Gas-Liquid and Liquid-Liquid Systems , 2001 .

[2]  Robert E. Henry,et al.  Transient Freezing of a Flowing Ceramic Fuel in a Steel Channel , 1976 .

[3]  R. Henry,et al.  Pressure Drop and Compressible Flow of Cryogenic Liquid-Vapor Mixtures , 1975 .

[4]  J. D. Gabor,et al.  Studies and experiments on heat removal from fuel debris in sodium , 1974 .

[5]  R. Lipinski.  A particle-bed dryout model with upward and downward boiling , 1980 .

[6]  P. Royl,et al.  Contributions from the ACRR in-pile experiments to the understanding of key phenomena influencing unprotected loss of flow accident simulations in LMFBRs , 1987 .

[7]  Vijay K. Dhir,et al.  Dryout Heat Fluxes for Inductively Heated Particulate Beds , 1977 .

[8]  J. D. Gabor,et al.  Core-debris accommodation research: status and plans. [LMFBR] , 1982 .

[9]  Lap Y. Cheng,et al.  Flow reversal power limit for the HFBR , 1997 .

[10]  H. Ninokata,et al.  A Recriticality-Free Fast Reactor Core Concept , 2000 .

[11]  Ikken Sato,et al.  Improvement of evaluation method for initiating-phase energetics based on CABRI-1 in-pile experiments , 1992 .

[12]  H. K. Fauske.  Comments on cladding and early fuel relocation in LMFBR core disruptive accidents , 1975 .

[13]  R. H. Nilson,et al.  Natural Convection in Porous Media with Heat Generation , 1977 .

[14]  Hans K. Fauske,et al.  Assessment of Fuel Coolant Interactions (FCIs) in the FBR Core Disruptive Accident (CDA) , 2002 .

[15]  M. Grolmes,et al.  Chapter 4, Part 2 – Liquid Metal Cooled Systems. Sodium Boiling Dynamics , 1981 .

[16]  D. R. Pedersen,et al.  Dryout Heat Fluxes in Particulate Beds Heated Through the Base , 1984 .

[17]  K. Hub,et al.  Fast breeder reactors. , 1972, Science.

[18]  H. Ninokata,et al.  Safety characteristics of the SCNES core , 1998 .

[19]  B. W. Spencer,et al.  Summary of treat experiments on oxide core-disruptive accidents. [LMFBR] , 1979 .

[20]  Werner Maschek,et al.  Investigations of Sloshing Fluid Motions in Pools Related to Recriticalities in Liquid-Metal Fast Breeder Reactor Core Meltdown Accidents , 1992 .

[21]  K. Koyama,et al.  Liquid–liquid interface stability in accelerating and constant-velocity tube flows , 2001 .

[22]  Robert E. Henry,et al.  PRESSURE-PULSE PROPAGATION IN TWO-PHASE ONE- AND TWO-COMPONENT MIXTURES. , 1971 .