Special state standard for unit neutron flux density in the measurement range of nuclear physics installations

1974 ◽  
Vol 17 (7) ◽  
pp. 990-995 ◽  
Author(s):  
R. D. Vasil'ev ◽  
V. P. Yaryna ◽  
V. D. Sevast'yanov
Keyword(s):  
Neutron Flux ◽  
Flux Density ◽  
State Standard ◽  
Nuclear Physics ◽  
Measurement Range ◽  
Special State Standard ◽  
Neutron Flux Density

Updated State Primary Special Standard of Units of Neutron Flux Density and Neutron Fluence for Nuclear-Physics Facilities

Atomic Energy ◽  
2020 ◽  
Vol 127 (4) ◽  
pp. 237-243
Author(s):  
V. D. Sevast’yanov ◽  
A. V. Yanushevich ◽  
O. I. Kovalenko ◽  
R. M. Shibaev
Keyword(s):  
Neutron Flux ◽  
Flux Density ◽  
Nuclear Physics ◽  
Neutron Fluence ◽  
Special Standard ◽  
Neutron Flux Density

Measuring parameters of slow neutron field in channel of a VVR-M-type reactor by means of detectors calibrated against state standard for units of thermal neutron flux density

1978 ◽  
Vol 21 (1) ◽  
pp. 114-118
Author(s):  
I. A. Yaritsyna ◽  
E. P. Kucheryavenko ◽  
T. M. Kuteeva ◽  
I. A. Kharitonov ◽  
G. Ya. Vasil'ev ◽  
...  
Keyword(s):  
Neutron Flux ◽  
Thermal Neutron ◽  
Flux Density ◽  
State Standard ◽  
Thermal Neutron Flux ◽  
Slow Neutron ◽  
Neutron Field ◽  
Type Reactor ◽  
Neutron Flux Density

Comparison of Neutron Flux Density in Carbon Prism filled with NaCl and Air

2020 ◽  
Author(s):  
Kamil Stevanka ◽  
Dusan Kral ◽  
Ondrej Stastny ◽  
Robert Holomb ◽  
Karel Katovsky ◽  
...  
Keyword(s):  
Neutron Flux ◽  
Flux Density ◽  
Neutron Flux Density

KNVK vacuum fission chambers for measuring neutron flux density

1987 ◽  
Vol 62 (3) ◽  
pp. 232-237
Author(s):  
E. K. Malyshev ◽  
S. V. Chuklyaev ◽  
O. I. Shchetinin
Keyword(s):  
Neutron Flux ◽  
Flux Density ◽  
Neutron Flux Density ◽  
Fission Chambers

scholarly journals Uncertainty Analysis of WWER-1000 Core Macroscopic Cross Sections due to Spectral Effects

2020 ◽  
pp. 39-46
Author(s):  
О. Kukhotska ◽  
I. Ovdiienko ◽  
M. Ieremenko
Keyword(s):  
Energy Spectrum ◽  
Isotopic Composition ◽  
Uncertainty Analysis ◽  
Neutron Flux ◽  
Flux Density ◽  
Cross Section ◽  
Cross Sections ◽  
Fuel Burnup ◽  
Thermophysical Parameters ◽  
Neutron Flux Density

The paper presents the results of uncertainty analysis of WWER‑1000 core macroscopic cross sections due to spectral effects during WWER‑1000 fuel burnup and the analysis of cross section sensitivity from thermophysical parameters of the calculated cell, which affect energy spectrum of neutron flux density. The calculation of changes in the isotopic composition during burnup and the preparation of macroscopic cross sections used the developed HELIOS computer model [1] for TVSA, which is currently operated at most Ukrainian WWER‑1000 units. The GRS approach applying Software for Uncertainty and Sensitivity Analyses (SUSA) [2] was chosen to assess the uncertainty of the macroscopic cross sections due to spectral effects and analysis of cross section sensitivity from thermophysical parameters. The spectral effect on macroscopic cross sections was taken into account by calculating the fuel burnup for variational sets of thermophysical parameters (fuel temperature, coolant temperature and density, boric acid concentration) prepared in advance by the SUSA program, as a result of which fuel isotopic composition vectors were obtained. After that, neutronic constants for the reference state were developed for each of the sets of isotopic composition, which corresponded to a certain set of thermophysical parameters. At the next stage, the uncertainty of macroscopic cross sections of the interaction due to the spectral effects on the isotopic composition of the fuel was analyzed using SUSA 4, followed by the analysis of cross section sensitivity from thermophysical parameters of the calculated cell affecting energy spectrum of neutron flux density. In the future, the uncertainty of two-group macroscopic diffusion constants can be used to estimate the overall uncertainty of neutronic characteristics in large-grid core calculations, in particular, in the safety analysis.

Determination of the neutron flux density at an unknown reactor power

1987 ◽  
Vol 14 (12) ◽  
pp. 677-680
Author(s):  
F. Tomášek
Keyword(s):  
Neutron Flux ◽  
Flux Density ◽  
Reactor Power ◽  
Neutron Flux Density

scholarly journals Determining the Fast Neutron Flux Density and Transmutation Level Measurements in ADS by the Use of a Threshold Nuclear Reaction

2018 ◽  
Vol 15 (5) ◽  
pp. 516-523
Author(s):  
M. Bielewicz ◽  
T. Hanusek ◽  
A. Jaskulak ◽  
M. Peryt ◽  
S. Tiutiunnikov
Keyword(s):  
Neutron Flux ◽  
Fast Neutron ◽  
Nuclear Reaction ◽  
Flux Density ◽  
Fast Neutron Flux ◽  
Neutron Flux Density

The influence of core power distribution on neutron flux density behind a pressure vessel of a VVER-1000 Mock Up in LR-0 reactor

2018 ◽  
Vol 142 ◽  
pp. 12-21
Author(s):  
Michal Košťál ◽  
Vojtěch Rypar ◽  
Evžen Losa ◽  
David Harut ◽  
Martin Schulc ◽  
...  
Keyword(s):  
Neutron Flux ◽  
Flux Density ◽  
Pressure Vessel ◽  
Power Distribution ◽  
Neutron Flux Density
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