PWR blowdown heat transfer separate-effects program - Thermal-Hydraulic Test Facility experimental data report for test 177. [Contains microfiche data]

Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 177, which is part of the ORNL Pressurized-Water Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. Objective of the program is to investigate the thermal-hydraulic phenomenon governing the energy transfer and transport processes that occur during a loss-of-coolant accident in a PWR system. Test 177 was conducted at the request of Idaho National Engineering Laboratory ''for use in the independent assessment of RELAP4/MOD6.'' Primary purpose of this report is to make the reduced instrument responses during test 177 available. The responses are presented in graphical form in engineering units and have been analyzed only to the extent necessary to assure reasonableness and consistency. The data are presented in microfiche form

Intracranial Vertebral Artery Dissections: Evolving Perspectives

Intracranial vertebral artery dissection (VAD) represents the underlying etiology in a significant percentage of posterior circulation ischemic strokes and subarachnoid hemorrhages. These lesions are particularly challenging in their diagnosis, management, and in the prediction of long-term outcome. Advances in the understanding of underlying processes leading to dissection, as well as the evolution of modern imaging techniques are discussed. The data pertaining to medical management of intracranial VADs, with emphasis on anticoagulants and antiplatelet agents, is reviewed. Surgical intervention is discussed, including, the selection of operative candidates, open and endovascular procedures, and potential complications. The evolution of endovascular technology and techniques is highlighted

Blowdown Heat Transfer Separate-Effects Program. Quarterly progress report, April-June 1980

Two transient film boiling tests were run - one in upflow, the other in downflow. The purpose of these tests was to provide experimental heat transfer data that could be used in an assessment of several film boiling correlations used in current thermal-hydraulic computer codes. The tests were designed to provide accurate posttest calculations of heat fluxes, surface temperatures, and local fluid conditions. THe Upflow Film Boiling Test 3.03.6AR was run on May 21, 1980, in the THTF. This test resulted in single-phase fluid flow at the test section inlet (subcooled) during the time the bundle was in high-flow film boiling. Furthermore, no flow reversal occurred during the test. Preliminary posttest analysis indicates that the calculation of mass flows at the inlet to the test section should result in numbers with relatively small uncertainties. We are optimistic that local fluid conditions can be calculated for this test with an accuracy sufficient for correlation evaluation. 7 figs

Blowdown heat transfer separate-effects program. Quarterly progress report, January-March 1980

Six additional bundle uncovery/recovery tests were performed in the Thermal-Hydraulic Test Facility during January, bringing the total number of these tests to eight. Data taken during the tests were found to be contaminated by numerous spurious spikes. Work to remove the spurious spikes is under way. Posttest analysis of the tests is approx.20% completed. The recovery portion of one of the tests will be analyzed by COBRA/TRAC, currently being developed by Pacific Northwest Laboratories (PNL). Work to debug the code for this application is in progress at PNL. The uncovery/recovery tests apparently caused damage to the 0-rings that form part of the loop pressure boundary. Refurbishment of the 0-ring seal system is being performed concurrently with scheduled loop modifications that include installation of ten in-bundle differential pressure instruments. Design, procurement, and fabrication of the in-bundle gamma densitometer system are continuing on schedule