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Monday, April 20, 2020 | History

3 edition of H.B. Robinson-2 pressure vessel benchmark found in the catalog.

H.B. Robinson-2 pressure vessel benchmark

I. Remec

H.B. Robinson-2 pressure vessel benchmark

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  • 2 Currently reading

Published by Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Supt. of Docs., U.S. G.P.O. [distributor] in Washington, DC .
Written in English

    Subjects:
  • Nuclear pressure vessels -- Standards -- United States.

  • Edition Notes

    Other titlesHB Robinson 2 pressure vessel benchmark.
    Statementprepared by I. Remec, F.B.K. Kam.
    ContributionsKam, F. B. K., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., Oak Ridge National Laboratory.
    The Physical Object
    FormatMicroform
    Paginationxi, 50 p.
    Number of Pages50
    ID Numbers
    Open LibraryOL15507158M


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H.B. Robinson-2 pressure vessel benchmark by I. Remec Download PDF EPUB FB2

@article{osti_, title = {H.B. Robinson-2 pressure vessel benchmark}, author = {Remec, I and Kam, F B.K.}, abstractNote = {The H. Robinson Unit 2 Pressure Vessel Benchmark (HBR-2 benchmark) is described and analyzed in this report. Analysis of the HBR-2 benchmark can be used as partial fulfillment of the requirements for the qualification of the methodology for.

Get this from a library. H.B. Robinson-2 pressure vessel benchmark. [I Remec; F B K Kam; U.S. Nuclear Regulatory Commission.

Office of Nuclear Regulatory Research. Division of Engineering Technology.; Oak Ridge National Laboratory.]. @article{osti_, title = {Analysis of dosimetry from the H.B. Robinson unit 2 pressure vessel benchmark using RAPTOR-M3G and ALPAN}, author = {Fischer, G A}, abstractNote = {Document available in abstract form only, full text of document follows: The dosimetry from the H.

Robinson Unit 2 Pressure Vessel Benchmark is analyzed with a suite of Westinghouse. on-2 Pressure Vessel Benchmark (HBR-2 benchmark) has been chosen for qualification of our methodology for pressure vessel neutron fluence calculations, as required by the U.S.

Nuclear Regulatory Commission Regulatory Guide The SCALE code package was used for modeling of the HBR-2 benchmark. The CSAS6 sequence of the. on-2 Pressure Vessel Benchmark (HBR-2 benchmark) is used for the qualification of pressure vessel neutron flux calculation methods and shielding calculations based on this model have been performed by Monte Carlo codes such as Author: Junjie Rao, Xiaotong Shang, Kan Wang.

Verification of Shielding Calculation Capability of RMC With on-2 Pressure Vessel Benchmark ICONE26 Neutron Transport Characteristics of a Nuclear Reactor Based Dynamic Neutron Imaging SystemAuthor: Shibiao Pan.

The SCALE general geometry package (SGGP) was used for modeling of the typical PWR facility based on the H. Robinson-2 Pressure Vessel Benchmark (HBR-2) critical core. Validation of the model (via detector reaction rates) was conducted in previous paper [ 12 ], where good agreement with referenced TORT results was obtained in accordance Cited by: 1.

The SCALE general geometry package (SGGP) was used for modeling of the typical PWR facility based on the on-2 Pressure Vessel Benchmark (HBR-2) critical core (Remec and Kam, ). Calculational results (reaction rates for six reactions) were compared with the benchmark results obtained by the TORT S N transport code in a previous Cited by: 4.

Performance Of A Monte-Carlo Solution To The H.B. Robinson-2 Pressure Vessel Dosimetry Benchmark A. Vasiliev, H.

Ferroukhi, E. Kolbe Annals of. Journal of The Korean Nuclear Society, Vol. 59, Pp. () Refined Monte Carlo Analysis Of The H.B.

Robinson-2 Reactor Pressure Vessel Dosimetry Benchmark R. Pittarello, A. Vasiliev, H. Ferroukhi, R. Chawla Annals of Nuclear Energy, Vol. 38, Pp. () Analysis Of An Ads Spurious Opening Event At A Bwr/6 By Means Of The.

Refined analysis, based on use of the Monte Carlo code MCNPX, is presented for the “H.B. Robinson-2 pressure vessel dosimetry benchmark”, which is. We used workstation with 32 GB of DDR3 RAM and Intel Core i5 CPU (4 × GHz). The SCALE code package was used for the typical PWR reactor shielding modeling with critical nuclear core description taken from the on-2 Pressure Vessel Benchmark (HBR-2) (Remec and Kam, ).The calculated dosimetry reaction rates for the in-core and out of the Cited by: 3.

Comparison of neutron data libraries for the analysis of the "H. ROBINSON-2 Pressure Vessel Bench August Journal- Korean Physical Society Alexander Vasiliev. Refined Monte Carlo analysis of the H.B. Robinson-2 reactor pressure vessel dosimetry benchmark. Pittarello On the effects of oxygen cross-sections in the fast neutron fluence analysis for a reactor pressure vessel scraping test.

Vasiliev; H Numerical neutronics benchmark study for inert matrix plutonium fuels in uranium dioxide. Modeling of on-2 Pressure Vessel Benchmark. No: Radomir Ječmenica, Mario Matijević, Dubravko Pevec, Krešimir Trontl - Croatia Fuel Depletion Modeling of a Gas-cooled Fast Reactor Using the SCALE6 Code Package.

No: Pouya Sabouri, Adrien Bidaud - France. For more accurate the estimation, new ORIGEN2 libraries are developed from the latest nuclear data library JENDL for cross sections and fission yields, and from other libraries for half-lives, and so on.

The new libraries are validated by PIE analyses of the sample fuels irradiated in Cooper, Calvert-Cliffs-1, H. Robinson-2, and Ohi On September 4, atGrand Gulf Nuclear Station entered three TS LCO Action Statements because RHR 'A' pump was declared inoperable.

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The broad perspective taken makes the book an appropriate introduction to the. The update from ENDF/B-IV toENDF/B-VI dpa rates when applied to the H. Robinson-2pressurized water reactor resulted in “up to ;4 % higher dparates in the region close to the pressure vessel outer surface”and in “slightly lower dpa.

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