Share

VVER-1000 Weapons-grade MOX Computational Benchmark Analysis

2000
Download VVER-1000 Weapons-grade MOX Computational Benchmark Analysis PDF Online Free

Author :
Release : 2000
Genre :
Kind : eBook
Book Rating : /5 ( reviews)

GET EBOOK


Book Synopsis VVER-1000 Weapons-grade MOX Computational Benchmark Analysis by :

Download or read book VVER-1000 Weapons-grade MOX Computational Benchmark Analysis written by . This book was released on 2000. Available in PDF, EPUB and Kindle. Book excerpt: Calculations of computational benchmark problems for the disposition of weapons-grade plutonium fuel in VVER-1000 reactors have been performed under the Joint US/Russian Fissile Material Disposition Program. The benchmarks cover pin cell, single fuel assembly, and multi-assembly structures with several different fuel types, moderator densities, and boron content for operational and off-normal conditions. Fuel depletion is performed to a burnup of 60 MWd/kgHM. The results of the analysis of the benchmarks with US and Russian code systems have been compared and indicated good agreement among the different methods and data.

Kirchenaustrittsbewegung im Freistaat Sachsen in der Zeit vom 4. Aug. 1919-31. Dez. 1926

1928
Download Kirchenaustrittsbewegung im Freistaat Sachsen in der Zeit vom 4. Aug. 1919-31. Dez. 1926 PDF Online Free

Author :
Release : 1928
Genre :
Kind : eBook
Book Rating : /5 ( reviews)

GET EBOOK


Book Synopsis Kirchenaustrittsbewegung im Freistaat Sachsen in der Zeit vom 4. Aug. 1919-31. Dez. 1926 by :

Download or read book Kirchenaustrittsbewegung im Freistaat Sachsen in der Zeit vom 4. Aug. 1919-31. Dez. 1926 written by . This book was released on 1928. Available in PDF, EPUB and Kindle. Book excerpt:

Analyses of Weapons-Grade MOX VVER-1000 Neutronics Benchmarks

2001
Download Analyses of Weapons-Grade MOX VVER-1000 Neutronics Benchmarks PDF Online Free

Author :
Release : 2001
Genre :
Kind : eBook
Book Rating : /5 ( reviews)

GET EBOOK


Book Synopsis Analyses of Weapons-Grade MOX VVER-1000 Neutronics Benchmarks by :

Download or read book Analyses of Weapons-Grade MOX VVER-1000 Neutronics Benchmarks written by . This book was released on 2001. Available in PDF, EPUB and Kindle. Book excerpt: A series of unit pin-cell benchmark problems have been analyzed related to irradiation of mixed oxide fuel in VVER-1000s (water-water energetic reactors). One-dimensional, discrete-ordinates eigenvalue calculations of these benchmarks were performed at ORNL using the SAS2H control sequence module of the SCALE-4.3 computational code system, as part of the Fissile Materials Disposition Program (FMDP) of the US DOE. Calculations were also performed using the SCALE module CSAS to confirm the results. The 238 neutron energy group SCALE nuclear data library 238GROUPNDF5 (based on ENDF/B-V) was used for all calculations. The VVER-1000 pin-cell benchmark cases modeled with SAS2H included zero-burnup calculations for eight fuel material variants (from LEU UO2 to weapons-grade MOX) at five different reactor states, and three fuel depletion cases up to high burnup. Results of the SAS2H analyses of the VVER-1000 neutronics benchmarks are presented in this report. Good general agreement was obtained between the SAS2H results, the ORNL results using HELIOS-1.4 with ENDF/B-VI nuclear data, and the results from several Russian benchmark studies using the codes TVS-M, MCU-RFFI/A, and WIMS-ABBN. This SAS2H benchmark study is useful for the verification of HELIOS calculations, the HELIOS code being the principal computational tool at ORNL for physics studies of assembly design for weapons-grade plutonium disposition in Russian reactors.

VVER-1000 MOX Core Computational Benchmark

2006 Burnup
Download VVER-1000 MOX Core Computational Benchmark PDF Online Free

Author :
Release : 2006
Genre : Burnup
Kind : eBook
Book Rating : 819/5 ( reviews)

GET EBOOK


Book Synopsis VVER-1000 MOX Core Computational Benchmark by : Expert Group on Reactor-based Plutonium Diposition

Download or read book VVER-1000 MOX Core Computational Benchmark written by Expert Group on Reactor-based Plutonium Diposition. This book was released on 2006. Available in PDF, EPUB and Kindle. Book excerpt:

Calculational Benchmark Problems for VVER-1000 Mixed Oxide Fuel Cycle

2000
Download Calculational Benchmark Problems for VVER-1000 Mixed Oxide Fuel Cycle PDF Online Free

Author :
Release : 2000
Genre :
Kind : eBook
Book Rating : /5 ( reviews)

GET EBOOK


Book Synopsis Calculational Benchmark Problems for VVER-1000 Mixed Oxide Fuel Cycle by :

Download or read book Calculational Benchmark Problems for VVER-1000 Mixed Oxide Fuel Cycle written by . This book was released on 2000. Available in PDF, EPUB and Kindle. Book excerpt: Standard problems were created to test the ability of American and Russian computational methods and data regarding the analysis of the storage and handling of Russian pressurized water reactor (VVER) mixed oxide fuel. Criticality safety and radiation shielding problems were analyzed. Analysis of American and Russian multiplication factors for fresh fuel storage for low-enriched uranium (UOX), weapons- (MOX-W) and reactor-grade (MOX-R) MOX differ by less than 2% for all variations of water density. For shielding calculations for fresh fuel, the ORNL results for the neutron source differ from the Russian results by less than 1% for UOX and MOX-R and by approximately 3% for MOX-W. For shielding calculations for fresh fuel assemblies, neutron dose rates at the surface of the assemblies differ from the Russian results by 5% to 9%; the level of agreement for gamma dose varies depending on the type of fuel, with UOX differing by the largest amount. The use of different gamma group structures and instantaneous versus asymptotic decay assumptions also complicate the comparison. For the calculation of dose rates from spent fuel in a shipping cask, the neutron source for UOX after 3-year cooling is within 1% and for MOX-W within 5% of one of the Russian results while the MOX-R difference is the largest at over 10%. These studies are a portion of the documentation required by the Russian nuclear regulatory authority, GAN, in order to certify Russian programs and data as being acceptably accurate for the analysis of mixed oxide fuels.

You may also like...