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Evaluation of postulated LOF (loss-of-flow) events in PRISM and SAFR

Description: The PRISM and SAFR designs, as currently proposed by DOE, are designed for ''inherent'', as opposed to ''engineered'', safety. Brookhaven National Laboratory is supporting the initial NRC review of these advanced LMR concepts. A loss-of-flow (LOF) accident coupled with a failure of the reactor shutdown system is one of the major safety concerns in the advanced liquid metal reactor (LMR) evaluation effort. The analysis discussed here covers: (1) primary pipe break without pump trip, (2) primary … more
Date: January 1, 1987
Creator: Chan, B. C.; Van Tuyle, G. J.; Slovik, G. C. & Aronson, A. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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The performance of 3500 MWth homogeneous and heterogeneous metal fueled core designs

Description: Performance parameters are calculated for a representative 3500 MWth homogeneous and a heterogeneous metal fueled reactor design. The equilibrium cycle neutronic characteristics, safety coefficients, control system requirements, and control rod worths are evaluated. The thermal-hydraulic characteristics for both configurations are also compared. The heavy metal fuel loading requirements and neutronic performance characteristics are also evaluated for the uranium startup option. 14 refs., 14 fig… more
Date: November 1, 1987
Creator: Turski, R. & Yang, Shi-tien
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

COMMIX analysis of the Sodium Heated Helical Coil Steam Generator

Description: This paper describes the COMMIX-HCSG computer program and compares predictions to data obtained from performance tests on a 76 MWt Helical Coil Steam Generator (HCSG) test unit. COMMIX-HCSG is a multi-dimensional thermal/hydraulic code that models both steady state and transient operation of an HCSG. The code solves a system of Navier-Stokes continuum equations that have been modified with a combination of volume and directional surface porosities and distributed resistances. This formulation p… more
Date: January 1, 1987
Creator: Kakarala, C. R.; Burge, S. W. & Sha, W. T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Thermal conductivity of Na/sub 3/(U/sub 1-y/Pu/sub y/)O/sub 4/: A preliminary in-pile determination

Description: During Run-Beyond-Cladding-Breach (RBCB) operation in an oxide LMR, the performance of a breached fuel element is intimately associated with the formation of fuel-sodium reaction product (FSRP), Na/sub 3/(U/sub 1-y/Pu/sub y/)O/sub 4/. In-pile experiments coupled with destructive examinations of breached fuel have consistently revealed noticeable changes in fuel structure accompanying FSRP formation at the fuel surface. Previous analyses have also indicated a significant impact of FSRP on fuel c… more
Date: January 1, 1987
Creator: Lee, M. J.; Lambert, J. D. B.; Ukai, S. & Odo, T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Operating experience with gas-bearing circulators in a high-pressure helium loop

Description: A high-pressure engineering test loop has been designed and constructed at the Oak Ridge National Laboratory for circulating helium through a test chamber at temperatures to 1000/sup 0/C. The purpose of this loop is to determine the thermal and structural performance of proposed components for the primary loops of gas-cooled nuclear reactors. Five MW of power is available to provide the required gas temperature at the test chamber, and an air-cooled heat exchanger, rated at 4.4 MW, serves as a … more
Date: January 1, 1987
Creator: Sanders, J.P.; Gat, Uri & Young, H.C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Demonstration of passive safety features in EBR-II

Description: Two tests of great importance to the design of future commercial nuclear power plants were carried out in the Experimental Breeder Reactor-II on April 3, 1986. These tests, (viewed by about 60 visitors, including 13 foreign LMR specialists) were a loss of flow without scram and a loss of heat sink without scram, both from 100% initial power. In these tests, inherent feedback shut the reactor down without damage to the fuel or other reactor components. This resulted primarily from advantageous c… more
Date: January 1, 1987
Creator: Planchon, H. P., Jr.; Golden, G. H. & Sackett, J. I.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

SASSYS analysis of EBR-II SHRT experiments

Description: SASSYS is a general purpose one-dimensional thermal-hydraulic LMR systems analysis code. The application of SASSYS to studies of protected and unprotected transient analysis of LMR designs, such as PRISM and SAFR, is commonplace. This usage requires that a strong validation base exist for SASSYS. Validation of a code such as SASSYS is made up of a variety of activities such as, application of separate component models to model problems where the solution is analytically known, cross comparison … more
Date: January 1, 1987
Creator: Hill, D.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Concept for a small, colocated fuel cycle facility for oxide breeder fuels

Description: As part of a United States Department of Energy (USDOE) program to examine innovative liquid-metal reactor (LMR) system designs over the past three years, the Oak Ridge National Laboratory (ORNL) and the Westinghouse Hanford Company (WHC) collaborated on studies of mixed oxide fuel cycle options. A principal effort was an advanced concept for a small integrated fuel cycle colocated with a 1300-MW(e) reactor station. The study provided a scoping design and a basis on which to proceed with implem… more
Date: January 1, 1987
Creator: Burch, W.D.; Stradley, J.G. & Lerch, R.E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Integrated oxidation-glass formation process for waste sodium disposal

Description: For permanent disposal of the large quantities of mildly contaminated waste liquid metals (primarily sodium) used as coolants in nuclear reactors, and currently stored at different DOE sites, it is necessary to convert the metal to a stable and environmentally acceptable disposable form at minimum cost. Work on air oxidation of sodium done by Mine Safety and Appliances, Inc. (MSA) in 1980 showed the feasibility of converting the metal to its oxides. This study investigates the development of an… more
Date: January 1, 1987
Creator: Rajan, J.B.; Kumar, R. & Vissers, D.R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Initial pipe break analyses for advanced LMR (liquid metal reactor) concepts using MINET

Description: In support of an initial NRC review of DOE sponsored advanced liquid metal reactors (LMRs), BNL has performed some very conservative calculations of postulated primary loop pipe breaks using the MINET Code. This report briefly describes the results obtained from these calculations. 5 refs., 2 figs.
Date: June 1, 1987
Creator: Van Tuyle, G. J.; Chan, B. C. & Slovik, G. C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

/sup 252/Cf-source-driven neutron noise measurements of subcriticality for a slab tank containing aqueous Pu-U nitrate

Description: In order to study nuclear criticality safety related to the development of fast breeder technology, /sup 252/Cf-source-driven neutron noise analysis measurements were performed with a Pu-U nitrate solution in a slab tank of various heights and thickness varying 11.43 cm to 19.05 cm. The results and conclusions of these experiments are (1) a capability to measure the subcriticality of a multiplying system of slab geometry to a k/sub eff/ as low as 0.7 was demonstrated, (2) calculated neutron mul… more
Date: August 1, 1987
Creator: Mihalczo, J.T.; Blakeman, E.D.; Ragan, G.E.; Kryter, R.C.; Robinson, R.C. & Seino, H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

A technique for computing bowing reactivity feedback in LMFBR's

Description: During normal or accidental transients occurring in a LMFBR core, the assemblies and their support structure are subjected to important thermal gradients which induce differential thermal expansions of the walls of the hexcans and differential displacement of the assembly support structure. These displacements, combined with the creep and swelling of structural materials, remain quite small, but the resulting reactivity changes constitute a significant component of the reactivity feedback coeff… more
Date: January 1, 1987
Creator: Finck, P.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Comparisons of power transfer functions and flow transfer functions

Description: Transfer functions may be used to calculate component feedbacks or temperature increments by convolution of the transfer function with the appropriate fractional change in system-quantity. Power-change transfer functions have been reported. The corresponding flow transfer functions for this case, and comparison with the power transfer functions, are reported here. Results of feedback simulation of ramped flow transients using flow transfer functions are also described.
Date: November 15, 1987
Creator: Grimm, K. N. & Meneghetti, D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Diagnostic technique for monitoring high temperature plasma dynamics

Description: A preliminary design for the adaptation of a pinhole experiment (PINEX) technique to the monitoring of the dynamics of high temperature plasmas is described. Specifically, this imaging technique uses a thick aperture, an efficient radiation converter, and highly intensified television cameras to provide real-time viewing of radiation sources such as the neutron emissions from d-d and d-t fusion reactions in controlled thermonuclear research devices. The neutron emission strengths, R approx. 5 x… more
Date: June 1, 1987
Creator: Lumpkin, A. H. & Pappas, D. S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Experience with lifetime limits for EBR-II core components

Description: The Experimental Breeder Reactor No. 2 (EBR-II) is operated for the US Department of Energy by Argonne National Laboratory and is located on the Idaho National Engineering Laboratory where most types of American reactor were originally tested. EBR-II is a complete electricity-producing power plant now in its twenty-fourth year of successful operation. During this long history the reactor has had several concurrent missions, such as demonstration of a closed Liquid-Metal Reactor (LMR) fuel cycle… more
Date: January 1, 1987
Creator: Lambert, J.D.B.; Smith, R.N. & Golden, G.H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Recommended practices in elevated temperature design: A compendium of breeder reactor experiences (1970-1986): An overview

Description: Significant experiences have been accumulated in the establishment of design methods and criteria applicable to the design of Liquid Metal Fast Breeder Reactor (LMFBR) components. The Subcommittee of the Elevated Temperature Design under the Pressure Vessel Research Council (PVRC) has undertaken to collect, on an international basis, design experience gained, and the lessons learned, to provide guidelines for next generation advanced reactor designs. This paper shall present an overview and des… more
Date: September 1, 1987
Creator: Wei, B. C.; Cooper, W. L., Jr. & Dhalla, A. K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Trends vs. reactor size of passive reactivity shutdown and control performance

Description: For LMR concepts, the goal of passive reactivity shutdown has been approached in the US by designing the reactors for favorable relationships among the power, power/flow, and inlet temperature coefficients of reactivity, for high internal conversion ratio (yielding small burnup control swing), and for a primary pump coastdown time appropriately matched to the delayed neutron hold back of power decay upon negative reactivity input. The use of sodium bonded metallic fuel pins has facilitated the … more
Date: January 1, 1987
Creator: Wade, D. C. & Fujita, E. K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

A simplified analysis of uncertainty propagation in inherently controlled ATWS events

Description: The quasi static approach can be used to provide useful insight concerning the propagation of uncertainties in the inherent response to ATWS events. At issue is how uncertainties in the reactivity coefficients and in the thermal-hydraulics and materials properties propagate to yield uncertainties in the asymptotic temperatures attained upon inherent shutdown. The basic notion to be quantified is that many of the same physical phenomena contribute to both the reactivity increase of power reducti… more
Date: January 1, 1987
Creator: Wade, D.C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Gas erosion of impeller housing in the operation of a high-temperature, high-pressure helium circulator

Description: Three gas-bearing circulators are installed in series in a high-pressure, high-temperature loop to provide helium flow up to 0.47 m/sup 3//s at a total head of 78 kJ/kg. The design pressure is 10.7 MPa, and temperatures of 1000/sup 0/C can be obtained in the test section. The inlet temperature to the circulators is limited to 450/sup 0/C. During a routine examination of the circulator, deep V-shaped grooves were found in the stationary surface of this cavity. At the same time, a very fine, dark… more
Date: January 1, 1987
Creator: Sanders, J.P.; Heestand, R.L. & Young, H.C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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The thermodynamics of pyrochemical processes for liquid metal reactor fuel cycles

Description: The thermodynamic basis for pyrochemical processes for the recovery and purification of fuel for the liquid metal reactor fuel cycle is described. These processes involve the transport of the uranium and plutonium from one liquid alloy to another through a molten salt. The processes discussed use liquid alloys of cadmium, zinc, and magnesium and molten chloride salts. The oxidation-reduction steps are done either chemically by the use of an auxiliary redox couple or electrochemically by the use… more
Date: January 1, 1987
Creator: Johnson, I.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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SASSYS-1 modelling of RVACS (Reactor Vessel Auxiliary Cooling System)/RACS (Reactor Air Cooling System) heat removal in an LMR (Liquid Metal Reactor)

Description: The SASSYS-1 Liquid Metal Reactor (LMR) systems analysis code contains a model for transient analysis of heat removal by a RVACS (Reactor Vessel Auxiliary Cooling System) or a RACS (Reactor Air Cooling System) in an LMR (Liquid Metal Reactor). This air-side RVACS/RACS model is coupled with the sodium-side primary loop thermal hydraulics model in SASSYS-1 to give a complete treatment of the problem. Application of this model to an unprotected loss-of-flow event in the PRISM reactor shows that in… more
Date: January 1, 1987
Creator: Dunn, F. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Gap and impact of LMR (Liquid Metal Reactor) piping systems and reactor components

Description: Because of high operation temperature, the LMR (Liquid Metal Reactor) plant is characterized by the thin-walled piping and components. Gaps are often present to allow free thermal expansion during normal plant operation. Under dynamic loadings, such as seismic excitation, if the relative displacement between the components exceeds the gap distance, impacts will occur. Since the components and piping become brittle over their design lifetime, impact is of important concern for it may lead to fra… more
Date: January 1, 1987
Creator: Ma, D.C.; Gvildys, J. & Chang, Y.W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Comparison of the SASSYS/SAS4A radial core expansion reactivity feedback model and the empirical correlation for FFTF

Description: The present emphasis on inherent safety for LMR designs has resulted in a need to represent the various reactivity feedback mechanisms as accurately as possible. The dominant negative reactivity feedback has been found to result from radial expansion of the core for most postulated ATWS events. For this reason, a more detailed model for calculating the reactivity feedback from radial core expansion has been recently developed for use with the SASSYS/SAS4A Code System. The purpose of this summar… more
Date: January 1, 1987
Creator: Wigeland, R.A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Pattern-recognition software detecting the onset of failures in complex systems

Description: A very general mathematical framework for embodying learned data from a complex system and combining it with a current observation to estimate the true current state of the system has been implemented using nearly universal pattern-recognition algorithms and applied to surveillance of the EBR-II power plant. In this application the methodology can provide signal validation and replacement of faulty signals on a near-real-time basis for hundreds of plant parameters. The mathematical framework, t… more
Date: 1987~
Creator: Mott, J. & King, R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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