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in creator/contributor: "Rose, S. D."

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Two-dimensional modeling of sodium boiling transients in simulated LMFBR fuel bundles

A two-dimensional code for analysis of sodium boiling in LMFBR fuel assemblies has been developed at ORNL. This code, THORAX, has been used to analyze tests in 19- and 61-pin electrically-heated, simulated LMFBR fuel assemblies in the THORS facility. THORAX has simulated well the transient growth of the two-dimensional boiling region and the resulting static flow instability leading to dryout. Extrapolation of results to a full size fuel pin bundle shows that two-dimensional effects are reduced… more

Date: January 1, 1982

Creator: Rose, S. D.; Dearing, J. F.; Carbajo, J. J.; Levin, A. E.; Montgomery, B. H. & Wantland, J. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Pretest predictions for degraded shutdown heat-removal tests in THORS-SHRS Assembly 1. [LMFBR]

The recent modification of the Thermal-Hydraulic Out-of-Reactor Safety (THORS) facility at ORNL will allow testing of parallel simulated fuel assemblies under natural-convection and low-flow forced-convection conditions similar to those that might occur during a partial failure of the Shutdown Heat Removal System (SHRS) of an LMFBR. An extensive test program has been prepared and testing will be started in September 1983. THORS-SHRS Assembly 1 consists of two 19-pin bundles in parallel with a t… more

Date: January 1, 1983

Creator: Rose, S. D. & Carbajo, J. J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Analysis of the OPERA 15-pin experiment with SABRE-2P. [LMFBR]

The OPERA (Out-of-Pile Expulsion and Reentry Apparatus) experiment simulates the initial phase of a pump coastdown without scram of a liquid-metal fast breeder reactor, specifically the Fast Flux Test Facility. The test section is a 15-pin 60/sup 0/ triangular sector designed to simulate a full-size 61-pin hexagonal bundle. A previous study indicates this to be an adequate simulation. In this paper, experimental results from the OPERA 15-pin experiment performed at ANL in 1982 are compared to a… more

Date: January 1, 1983

Creator: Rose, S. D. & Carbajo, J. J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Evaluation of COBRA III-C and SABRE-I (wire wrap version) computational results by comparison with steady-state data from a 19-pin internally guard heated sodium cooled bundle with a six-channel central blockage (THORS bundle 3C). [LMFBR]

The predicted computational results of two well-known sub-channel analysis codes, COBRA-III-C and SABRE-I (wire wrap version), have been evaluated by comparison with steady state temperature data from the THORS Facility at ORNL. Both codes give good predictions of transverse and axial temperatures when compared with wire wrap thermocouple data. The crossflow velocity profiles predicted by these codes are similar which is encouraging since the wire wrap models are based on different assumptions.

Date: January 1, 1979

Creator: Dearing, J. F.; Rose, S. D. & Nelson, W. R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Natural circulation in simulated LMFBR fuel assemblies

Natural circulation experiments have been performed using simulated liquid metal fast breeder reactor fuel assemblies in the Thermal-Hydraulic Out-of-Reactor Safety (THORS) facility, an engineering-scale sodium loop. Objective of these tests has been to provide experimental data under conditions that might be encountered during a partial or total loss of the shutdown heat removal system (SHRS) in a reactor. The experiments have included single- and two-phase tests under quasi-steady and transie… more

Date: January 1, 1985

Creator: Levin, A. E.; Carbajo, J. J.; Lloyd, D. B.; Montgomery, B. H.; Rose, S. D. & Wantland, J. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Comparison of COBRA III-C and SABRE-1 (wire-wrap version) computational results with steady-state data from a 19-pin internally guard heated sodium-cooled bundle with a six-channel central blockage (THORS Bundle 3C). [LMFBR]

Computational thermal-hydraulic models of a 19-pin, electrically heated, wire-wrap liquid-metal fast breeder reactor test bundle were developed using two well-known subchannel analysis codes, COBRA III-C and SABRE-1 (wire-wrap version). These two codes use similar subchannel control volumes for the finite difference conservation equations but vary markedly in solution strategy and modeling capability. In particular, the empirical wire-wrap-forced diversion crossflow models are different. Surpri… more

Date: January 1, 1979

Creator: Dearing, J. F.; Nelson, W. R. & Rose, S. D.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Forced-convection boiling tests performed in parallel simulated LMR fuel assemblies

Forced-convection tests have been carried out using parallel simulated Liquid Metal Reactor fuel assemblies in an engineering-scale sodium loop, the Thermal-Hydraulic Out-of-Reactor Safety facility. The tests, performed under single- and two-phase conditions, have shown that for low forced-convection flow there is significant flow augmentation by thermal convection, an important phenomenon under degraded shutdown heat removal conditions in an LMR. The power and flows required for boiling and dr… more

Date: April 21, 1985

Creator: Rose, S. D.; Carbajo, J. J.; Levin, A. E.; Lloyd, D. B.; Montgomery, B. H. & Wantland, J. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Sodium boiling dryout correlation for LMFBR fuel assemblies

Under certain postulated accident conditions for a Liquid Metal Fast Breeder Reactor (LMFBR), such as the failure of the shutdown heat removal system (SHRS), sodium boiling and clad dryout might occur in the fuel assemblies. It is important to predict the time from boiling inception to dryout, since sustained clad dryout will result in core damage. In this paper a dryout correlation is presented. This correlation is based on 21 boiling tests which resulted in dryout from the THORS BUNDLE 6A, a … more

Date: January 1, 1984

Creator: Carbajo, J. J. & Rose, S. D.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Steady state temperature profiles in two simulated liquid metal reactor fuel assemblies with identical design specifications

Temperature data from steady state tests in two parallel, simulated liquid metal reactor fuel assemblies with identical design specifications have been compared to determine the extent to which they agree. In general, good agreement was found in data at low flows and in bundle-center data at higher flows. Discrepancies in the data wre noted near the bundle edges at higher flows. An analysis of bundle thermal boundary conditions showed that the possible eccentric placement of one bundle within t… more

Date: January 1, 1985

Creator: Levin, A. E.; Carbajo, J. J.; Lloyd, D. B.; Montgomery, B. H.; Rose, S. D. & Wantland, J. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Core coolability limits in LMFBR loss-of-heat-sink accidents

Considerable attention has been devoted to the loss-of-heat-sink (LOHS) accident after successful reactor shutdown in a liquid-metal fast breeder reactor (LMFBR). It has been estimated that this accident accounts for more than 80% of the risk of hypothetical core disruptive accidents; therefore, attention should be focused on this specific contributor. In this paper, an analytical study has been performed to estimate the decay heat powers that can be safely removed by sustained free convection … more

Date: January 1, 1984

Creator: Rose, S. D. & Carbajo, J. J.

Item Type: Article

Partner: UNT Libraries Government Documents Department