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.
Download or read book MELCOR Verification Benchmarking and Applications Experience at BNL written by and published by . This book was released on 1992 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper presents a summary of MELCOR Verification, Benchmarking and Applications experience at Brookhaven National Laboratory (BNL), sponsored by the US Nuclear Regulatory Commission (NRC). Under MELCOR verification over the past several years, all released versions of the code were installed on BNL's computer system, verification exercises were performed, and defect investigation reports were sent to SNL. Benchmarking calculations of integral severe fuel damage tests performed at BNL have helped to identify areas of modeling strengths and weaknesses in MELCOR; the most appropriate choices for input parameters; selection of axial nodalization for core cells and heat structures; and workarounds that extend the capabilities of MELCOR. These insights are explored in greater detail in the paper, with the help of selected results and comparisons. Full plant applications calculations at BNL have helped to evaluate the ability of MELCOR to successfully simulate various accident sequences and calculate source terms to the environment for both BWRs and PWRs. A summary of results, including timing of key events, thermal-hydraulic response, and environmental releases of fission products are presented for selected calculations, along with comparisons with Source Term Code Package (STCP) calculations of the same sequences. Differences in results are explained on the basis of modeling differences between the two codes. The results of a sensitivity calculation are also shown. The paper concludes by highlighting some insights on bottomline issues, and the contribution of the BNL program to MELCOR development, assessment, and the identification of user needs for optimum use of the code.
Download or read book MELCOR Verification Benchmarking and Applications Experience at BNL written by and published by . This book was released on 1992 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Independent Assessment of MELCOR as a Severe Accident Thermal hydraulic written by and published by . This book was released on 1994 with total page 11 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 called ''MELCOR Verification, Benchmarking, and Applications, '' whose aim is to provide independent assessment of MELCOR as a severe accident thermal-hydraulic/source term analysis tool. The scope of this program is to perform quality control verification on all released versions of MELCOR, to benchmark MELCOR against more mechanistic codes and experimental data from severe fuel damage tests, and to evaluate the ability of MELCOR to simulate long-term severe accident transients in commercial LWRs, by applying the code to model both BWRs and PWRs. Under this program, BNL provided input to the NRC-sponsored MELCOR Peer Review, and is currently contributing to the MELCOR Cooperative Assessment Program (MCAP). This paper presents a summary of MELCOR assessment efforts at BNL and their contribution to NRC goals with respect to MELCOR.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1995 with total page 782 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 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 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 Nuclear Power Plant Severe Accident Research Plan written by John T. Larkins and published by . This book was released on 1983 with total page 146 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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 Nuclear Safety written by and published by . This book was released on 1984 with total page 928 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book INIS Atomindex written by and published by . This book was released on 1995 with total page 640 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 1996 with total page 674 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reauthorization of the Nuclear Regulatory Commission for fiscal years 1988 and 1989 and nuclear emergency planning written by United States. Congress. Senate. Committee on Environment and Public Works. Subcommittee on Nuclear Regulation and published by . This book was released on 1987 with total page 456 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Transactions of the Eleventh Water Reactor Safety Research Information Meeting written by and published by . This book was released on 1983 with total page 392 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 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:
