Mixing requirements for the limiting fuel-coolant interactions in liquid metal fast breeder reactors
Abstract
An estimation of the mixing requirements for the limiting fuel-coolant interactions in two specific liquid metal cooled fast reactors, the Fast Flux Test Facility (FFTF) and the Clinch River Breeder Reactor (CRBR), has been undertaken. The mixing requirements were represented in terms of the limiting mixing time constants. These constants were determined with the Argonne parametric FCI Computer Model for a range of core involvements. Specifically, fuel masses used ranged from as low as one-seventh of the core to a full core involvement. In general, conservative values for additional FCI input parameters were assumed such that the results would be conservative. With the results in hand, several mechanisms were investigated to determine what limiting effects they could have on the mixing rates of the fuel and coolant during an FCI. The energy requirements for mixing were investigated. The results, however, provided no limiting effects. A solidification limited fragmentation model was also investigated. Although this model provided no absolute limiting effects, it did show that fuel particle sizes of a certain size could indeed limit the fuel-coolant mixing rates. Additionally, the limiting effects were found to be much less significant for UC fuel. The third mechanism that was investigated concerned themore »
- Authors:
- Publication Date:
- Research Org.:
- Massachusetts Inst. of Tech., Cambridge (USA). Dept. of Nuclear Engineering
- Sponsoring Org.:
- US Energy Research and Development Administration (ERDA)
- OSTI Identifier:
- 7225054
- Report Number(s):
- COO-2781-8TR
TRN: 77-009150
- DOE Contract Number:
- EY-76-S-02-2781
- Resource Type:
- Technical Report
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; CLINCH RIVER BREEDER REACTOR; FUEL-COOLANT INTERACTIONS; FFTF REACTOR; LMFBR TYPE REACTORS; REACTOR CORE DISRUPTION; FRAGMENTATION; HEAT TRANSFER; MATHEMATICAL MODELS; MIXING; SODIUM; THERMODYNAMICS; URANIUM CARBIDES; URANIUM DIOXIDE; URANIUM NITRIDES; ACCIDENTS; ACTINIDE COMPOUNDS; ALKALI METALS; BREEDER REACTORS; CARBIDES; CARBON COMPOUNDS; CHALCOGENIDES; ELEMENTS; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; METALS; NITRIDES; NITROGEN COMPOUNDS; OXIDES; OXYGEN COMPOUNDS; PNICTIDES; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SODIUM COOLED REACTORS; TEST REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; 220900* - Nuclear Reactor Technology- Reactor Safety; 210500 - Power Reactors, Breeding; 220600 - Nuclear Reactor Technology- Research, Test & Experimental Reactors
Citation Formats
Lenz, Jr, W F. Mixing requirements for the limiting fuel-coolant interactions in liquid metal fast breeder reactors. United States: N. p., 1976.
Web. doi:10.2172/7225054.
Lenz, Jr, W F. Mixing requirements for the limiting fuel-coolant interactions in liquid metal fast breeder reactors. United States. doi:10.2172/7225054.
Lenz, Jr, W F. Mon .
"Mixing requirements for the limiting fuel-coolant interactions in liquid metal fast breeder reactors". United States.
doi:10.2172/7225054. https://www.osti.gov/servlets/purl/7225054.
@article{osti_7225054,
title = {Mixing requirements for the limiting fuel-coolant interactions in liquid metal fast breeder reactors},
author = {Lenz, Jr, W F},
abstractNote = {An estimation of the mixing requirements for the limiting fuel-coolant interactions in two specific liquid metal cooled fast reactors, the Fast Flux Test Facility (FFTF) and the Clinch River Breeder Reactor (CRBR), has been undertaken. The mixing requirements were represented in terms of the limiting mixing time constants. These constants were determined with the Argonne parametric FCI Computer Model for a range of core involvements. Specifically, fuel masses used ranged from as low as one-seventh of the core to a full core involvement. In general, conservative values for additional FCI input parameters were assumed such that the results would be conservative. With the results in hand, several mechanisms were investigated to determine what limiting effects they could have on the mixing rates of the fuel and coolant during an FCI. The energy requirements for mixing were investigated. The results, however, provided no limiting effects. A solidification limited fragmentation model was also investigated. Although this model provided no absolute limiting effects, it did show that fuel particle sizes of a certain size could indeed limit the fuel-coolant mixing rates. Additionally, the limiting effects were found to be much less significant for UC fuel. The third mechanism that was investigated concerned the limiting effects of the finite fuel release rates as a result of TOP accidents in the FFTF. Equivalent mixing time constants based on the fuel release rates were shown to be greater than the limiting values. Thus, this mechanism was shown to be limiting for the particular accident sequence investigated.},
doi = {10.2172/7225054},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Nov 01 00:00:00 EST 1976},
month = {Mon Nov 01 00:00:00 EST 1976}
}
Save to My Library
You must Sign In or Create an Account in order to save documents to your library.
-
Anticipated transients without scram for light water reactors: implications for liquid metal fast breeder reactors
The proposed ATWS acceptance criteria for LWRs (as specified in NUREG-0460) are in principle, applicable to LMFBRs. For LMFBRs, the major criterion will be the assurance that the plant protection system (shutdown or scram) has a sufficiently high reliability (low failure rate) so that core disruptive accidents (as currently defined) will lie outside the design basis. For early plants, however, mitigating systems may also be required. Alternative accident scenarios for LMFBRs, which are initiated from the shutdown state or may lead to potential core disruptive accidents even following scram, need to be examined in greater detail. The proposed LWR-ATWS criteriamore » -
Anticipated transients without scram for light water reactors: implications for liquid metal fast breeder reactors
In the design of light water reactors (LWRs), protection against anticipated transients (e.g., loss of normal electric power and control rod withdrawal) is provided by a highly reliable scram, or shutdown system. If this system should become inoperable, however, the transient could lead to a core meltdown. The Nuclar Regulatory Commission (NRC) has proposed, in NUREG-0460 (1), new requirements (or acceptance criteria) for anticipated transients without scram (ATWS) events and the manner in which they could be considered in the design and safety evaluation of LWRs. This note assesses the potential impact of the proposed LWR-ATWS criteria on the liquidmore » -
Transient limits of the Fast Flux Test Facility with respect to the passive safety program for liquid-metal fast breeder reactors. Master's thesis
Reviewing the history behind the transient limits, including how they are presently calculated, teaches what affects the Fast Flux Test Facility (FFTF) capabilities. The purpose of this thesis is, therefore, to give the passive safety planners a compact source of this information. It covers the original methodology for calculating the transient limits, the NRC's criticisms of it, and the subsequent revisions at a level thorough enough for a basic understanding. There is also a chapter on metal fuel to provide qualitative information that will influence its use in the FFTF during transient tests. Finally, the conclusion indicates the direction HEDLmore »