Download or read book PWR Blowdown Heat Transfer Separate effects Program Thermal Hydraulic Test Facility Experimental Data Report for Test 177 Contains Microfiche Data written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Download or read book PWR Blowdown Heat Transfer Separate Effects Program Thermal Hydraulic Test Facility Experimental Data Report for Test 167R written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 167R, which is part of the ORNL Pressurized-Water Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The 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 167R was conducted to obtain thermal-hydraulic and CHF information in THTF bundle 1 with an intact cold leg. The primary purpose of this report is to make the reduced instrument responses during test 167R available. These are presented in graphical form in engineering units and have been analyzed only to the extent necessary to ensure reasonableness and consistency.
Download or read book PWR Blowdown Heat Transfer Separate Effects Program Thermal Hydraulic Test Facility Experimental Data Report for Test 168R written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 168R, which is part of the ORNL Pressurized-Water Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The 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 168R was conducted to obtain thermal-hydraulic and CHF information in the THTF bundle 1 to compare with tests having intact legs (166S and 167R). The primary purpose of this report is to make the reduced instrument responses during test 168R 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.
Download or read book PWR Blowdown Heat Transfer Separate effects Program written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 100, which is part of the ORNL Pressurized-Water-Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The 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 100 was conducted to investigate the response of heater rod bundle 1 and instrumented spool pieces with flow homogenizing screens to a double-ended rupture with equal break areas at the test section inlet and outlet. The primary purpose of this report is to make the reduced instrument responses during test 100 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.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1985 with total page 672 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book PWR Blowdown Heat Transfer Separate effects Program written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 104, which is part of the ORNL Pressurized-Water Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The 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 the PWR system. Test 104 was conducted to obtain CHF in bundle 1 under blowdown conditions. The primary purpose of this report is to make the reduced instrument responses during test 104 available.
Download or read book PWR Blowdown Heat Transfer Separate Effects Program written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 151, which is part of the ORNL Pressurized-Water Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The 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 151 was conducted to obtain CHF information in the THTF bundle 1 containing four unpowered rods.
Download or read book PWR Blowdown Heat Transfer Separate Effects Program written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 101, which is part of the ORNL Pressurized-Water Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The 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 101 was conducted to investigate the thermal-hydraulic response of bundle 1 and the main heat exchangers to powered operation and a single-ended rupture at the test section outlet.
Download or read book PWR Blowdown Heat Transfer Separate Effects Program Thermal Hydraulic Test Facility Experimental Data Report for Test 103 written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 103, which is part of the ORNL Pressurized-Water Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The 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.
Download or read book PWR Blowdown Heat Transfer Separated Effects Program Thermal Hydraulic Test Facility Experimental Data Report for Test 102 PWR written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 102, which is part of the ORNL Pressurized-Water Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The 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 102 was conducted to investigate the thermal-hydraulic response of bundle 1 under full-power steady-state and blowdown conditions.
Download or read book PWR Blowdown Heat Transfer Separate effects Program Data Evaluation Report written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Selected reduced instrument responses and analyses of the indicated phenomena are presented for Thermal-Hydraulic Test Facility (THTF) test series 100, which is part of the PWR Blowdown Heat Transfer Separate-Effects Program. The objective of the program is to investigate the thermal-hydraulic phenomena that govern the energy transfer and transport processes occurring during a postulated loss-of-coolant accident in a pressurized-water reactor system. Comparisons are made between the trends indicated by the reduced instrument responses and the thermal-hydraulic transient simulator RELAP4/MOD5 (update 2) to aid in understanding the phenomenological sequences. The results of verification studies of RELAP's performance in prediction of the THTF data are presented.
Download or read book Monthly Catalogue United States Public Documents written by and published by . This book was released on 1982 with total page 650 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Monthly Catalog of United States Government Publications written by and published by . This book was released on 1982 with total page 1060 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Government Reports Announcements Index written by and published by . This book was released on 1982-06 with total page 1142 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Project Description written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The ORNL Pressurized-Water Reactor Blowdown Heat Transfer (PWR-BDHT) Program is an experimental separate-effects study of the relations among the principal variables that can alter the rate of blowdown, the presence of flow reversal and rereversal, time delay to critical heat flux, the rate at which dryout progresses, and similar time-related functions that are important to LOCA analysis. Primary test results will be obtained from the Thermal-Hydraulic Test Facility (THTF), a large nonnuclear pressurized-water loop that incorporates a 49-rod electrically heated bundle. Supporting experiments will be carried out in two additional test loops - the Forced Convection Test Facility (FCTF), a small high-pressure facility in which single heater rods can be tested in annular geometry; and an air-water loop which is used to evaluate two-phase flow-measuring instrumentation.
Download or read book Experiment Data Report for Semiscale Mod 1 Test S 02 8 Blowdown Heat Transfer Test PWR written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Recorded test data are presented for Test S-02-8 of the Semiscale Mod-1 blowdown heat transfer test series. This test is one of several Semiscale Mod-1 experiments conducted to investigate the thermal and hydraulic phenomena accompanying a hypothesized loss-of-coolant accident in a pressurized water reactor system, and to provide a data base for a regulatory standard problem. Test S-02-8 was conducted from an initial cold leg fluid temperature of 542°F and an initial pressure of 2,262 psia. A simulated double-ended offset shear cold leg break was used to investigate the system response to a depressurization transient with full core power (1.6 MW). An electrically heated core was used in the pressure vessel to simulate the effects of a nuclear core. System flow was set to achieve the full design core temperature differential of 66°F. The flow resistance of the intact loop was based on core area scaling. During system depressurization, core power was reduced from the initial level of 1.6 MW to simulate the surface heat flux response of nuclear fuel rods until such time that departure from nucleate boiling occurs. Blowdown to the pressure suppression system was accomplished without simulated emergency core cooling injection or pressure suppression system coolant spray. The purpose of the report is to make available the uninterpreted data from Test S-02-8 for future data analysis andtest results reporting activities. The data, presented in the form of graphs in engineering units, have been analyzed only to the extent necessary to assure that they are reasonable and consistent.
Download or read book Experiment Data Report for Semiscale Mod 1 Tests S 02 9 and S 02 9A blowdown Heat Transfer Tests written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Recorded test data are presented for Tests S-02-9 and S-02-9A of the Semiscale Mod-1 blowdown heat transfer test series. These tests are among several Semiscale Mod-1 experiments conducted to investigate the thermal and hydraulic phenomena accompanying a hypothesized loss-of-coolant accident in a water-cooled nuclear reactor system and to provide data for the assessment of the Loss-of-Fluid Test (LOFT) design basis. Tests S-02-9 and S-02-9A were conducted from initial cold leg fluid temperatures of 542 and 544$sup 0$F, respectively, and initial pressures of 2,253 and 2,263 psia, respectively. A simulated double- ended offset shear cold leg break was used to investigate the system response to a depressurization transient with full core power (1.6 MW). An electrically heated core was used in the pressure vessel to simulate the effects of a nuclear core. System flow was set to achieve full core temperature differential (66$sup 0$F). The flow resistance of the intact loop was based on core area scaling. During system depressurization, core power was reduced from the initial level of 1.6 MW in such a manner as to simulate the surface heat flux response of the LOFT nuclear fuel rods until such time that departure from nucleate boiling occurs. Both tests were conducted with a flat radial power profile. Blowdown to the pressure suppression system was accompanied by simulated emergency core cooling injection into both the intact and broken loops. However, pressure suppression system coolant spray was not used. (auth).
