Download or read book MELCOR Simulation of the PBF Power Burst Facility Severe Fuel Damage Test 1 1 written by and published by . This book was released on 1989 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper describes a MELCOR version 1.7.1 simulation of the Power Burst Facility (PBF) Severe Fuel Damage (SFD) 1-1 test. The input data for the simulation was obtained from the SFD 1-1 Test Results Report and from SCDAP input. Results are presented for the transient two-phase interface level in the core, fuel and clad temperatures at various elevations in the fuel bundle, clad oxidation, hydrogen generation, fission product release, and heat transfer to the surrounding structures. Comparisons are made with experimental data and predictions from STCP and the NRC's mechanistic code SCDAP (version 18). 6 refs., 12 figs.

Download or read book MELCOR Modeling of the PBF Power Burst Facility Severe Fuel Damage Test 1 4 written by and published by . This book was released on 1990 with total page 6 pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper describes a MELCOR Version 1.8 simulation of the Power Burst Facility (PBF) Severe Fuel Damage (SFD) Test 1--4. The input data for the analysis were obtained from the Test Results Report and from SCDAP/RELAP5 input. Results are presented for the transient liquid level in the test bundle, clad temperatures, shroud temperatures, clad oxidation and hydrogen generation, bundle geometry changes, fission product release, and heat transfer to the bypass flow. Comparisons are made with experimental data and with SCDAP/RELAP5 calculations. 10 refs., 7 figs.

Download or read book MELCOR Simulation of the PBF Severe Fuel Damage Test 1 1 written by and published by . This book was released on 1989 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book MELCOR Modeling of the PBF Severe Fuel Damage Test 1 4 written by and published by . This book was released on 1990 with total page 6 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Energy Research Abstracts written by and published by . This book was released on 1990 with total page 840 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Power Burst Facility PBF Severe Fuel Damage Test 1 4 Test Results Report written by and published by . This book was released on 1989 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: A comprehensive evaluation of the Severe Fuel Damage (SFD) Test 1-4 performed in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory is presented. Test SFD 1-4 was the fourth and final test in an internationally sponsored light water reactor severe accident research program, initiated by the US Nuclear Regulatory Commission. The overall technical objective of the test was to contribute to the understanding of fuel and control rod behavior, aerosol and hydrogen generation, and fission product release and transport during a high-temperature, severe fuel damage transient. A test bundle, comprised of 26 previously irradiated (36,000 MWd/MtU) pressurized water-reactor-type fuel rods, 2 fresh instrumented fuel rods, and 4 silver-indium-cadmium control rods, was surrounded by an insulating shroud and contained in a pressurized in-pile tube. The experiment consisted of a 1.3-h transient at a coolant pressure of 6.95 MPa in which the inlet coolant flow to the bundle was reduced to 0.6 g/s while the bundle fission power was gradually increased until dryout, heatup, cladding rupture, and oxidation occurred. With sustained fission power and heat from oxidation, temperatures continued to rise rapidly, resulting in zircaloy and control rod absorber alloy melting, fuel liquefaction, material relocation, and the release of hydrogen, aerosols, and fission products. The transient was terminated over a 2100-s time span by slowly reducing the reactor power and cooling the damaged bundle with argon gas. A description and evaluation of the major phenomena, based upon the response of on-line instrumentation, analysis of fission product and aerosol data, postirradiation examination of the fuel bundle, and calculations using the SCDAP/RELAP5 computer code, are presented. 40 refs., 160 figs., 31 tabs.

Download or read book ERDA Energy Research Abstracts written by and published by . This book was released on 1989 with total page 848 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Power Burst Facility PBF Severe Fuel Damage Test 1 4 written by David A. Petti and published by . This book was released on 1989 with total page 518 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Heat Transfer Philadelphia 1989 written by Salim B. Yilmaz and published by . This book was released on 1989 with total page 492 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Radioactive Waste Management written by and published by . This book was released on 1991 with total page 382 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book AIChE Symposium Series written by American Institute of Chemical Engineers and published by . This book was released on 1989 with total page 858 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Nuclear Thermal Hydraulic and Two Phase Flow written by Jun Wang and published by Frontiers Media SA. This book was released on 2018-10-11 with total page 120 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear energy is one of the most important clear energy and contributes more than 10% electric power to human society in the past decades of years. The nuclear thermal hydraulic and two-phase flow is one of the basic branches of nuclear technology and provides structure design and safety analysis to the nuclear power reactors. In the new century, the basic theoretical research of thermal hydraulic and two-phase flow, and innovative design for the next generation nuclear power plants (especially for the small modular reactor and molten salt reactor), along with other nuclear branches, constantly support the development of nuclear technology.

Download or read book Transactions of the American Nuclear Society written by and published by . This book was released on 1988 with total page 628 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book PBF Severe Fuel Damage Test 1 1 written by Zoel R. Martinson and published by . This book was released on 1986 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book PBF Severe Fuel Damage Test 1 1 Appendices A through I written by Zoel R. Martinson and published by . This book was released on 1986 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Power Burst Facility written by James G. Smith and published by . This book was released on 1972 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Melcor Benchmarking Against Integral Severe Fuel Damage Tests written by and published by . This book was released on 1994 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: MELCOR is a fully integrated computer code that models all phases of the progression of severe accidents in light water reactor nuclear power plants, and is being developed for the US Nuclear Regulatory Commission (NRC) by Sandia National Laboratories (SNL). Brookhaven National Laboratory (BNL) has a program with the NRC to provide independent assessment of MELCOR, and a very important part of this program is to benchmark MELCOR against experimental data from integral severe fuel damage tests and predictions of that data from more mechanistic codes such as SCDAP or SCDAP/RELAP5. Benchmarking analyses with MELCOR have been carried out at BNL for five integral severe fuel damage tests, namely, PBF SFD 1-1, SFD 1-4, and NRU FLHT-2, FLHT-4, and FLHT-5. This paper presents a summary of these analyses, and their role in identifying areas of modeling strengths and weaknesses in MELCOR.