scholarly journals Modelling of Impurity Activation in the RBMK Reactor Graphite Using MCNPX

2011 ◽  
Vol 2 (0) ◽  
pp. 421-426 ◽  
Author(s):  
Rita PLUKIENĖ ◽  
Artūras PLUKIS ◽  
Andrius PUZAS ◽  
Vidmantas REMEIKIS ◽  
Grigorijus DUŠKESAS ◽  
...  
Keyword(s):  
Rbmk Reactor ◽  
Reactor Graphite

scholarly journals ESTIMATION OF THE GENERATION OF 13C AND 14C IN THE REACTOR GRAPHITE USING MCNP6 MODELLING, ISOTOPE RATIO MASS SPECTROMETRY AND 14C MEASUREMENT TECHNIQUE

2021 ◽  
Vol 247 ◽  
pp. 16004
Author(s):  
R. Plukienė ◽  
E. Lagzdina ◽  
J. Garankin ◽  
A. Garbaras ◽  
A. Gudelis ◽  
...  
Keyword(s):  
Mass Spectrometry ◽  
Isotope Ratio ◽  
Specific Activity ◽  
Computer Modelling ◽  
Isotope Ratio Mass Spectrometry ◽  
Rbmk Reactor ◽  
Research Centre ◽  
Treatment Technology ◽  
Reactor Graphite ◽  
Irradiated Graphite

Characterization of irradiated graphite in terms of 14C activity is crucial for the optimization of treatment technology: geological disposal, landfill storage, recycling, etc. The main contributor to 14C generation in the RBMK reactor graphite is 14N(n, p)14C reaction. The generation of carbon isotopes 13C and 14C in the virgin RBMK graphite samples irradiated at the LVR-15 research reactor (Research Centre Řež, Ltd.) were investigated in order to obtain the impurity concentration level of 14N. Afterwards the modeling of graphite activation in the RBMK-1500 reactor was performed by computer code MCNP6 using obtained 14N impurity concentrations and new nuclear data libraries. The irradiation parameters – neutron fluence have been checked by method based on coupling of stable isotope ratio mass spectrometry and computer modelling. The activity of 14C in the different constructions of irradiated graphite of the RBMK-1500 reactor has been measured by the β spectrometry technique (LSC) and has been compared with the simulated one. Obtained results have indicated the importance of 14C production from 14N in the RBMK-1500 reactor and in the LVR-15 neutron spectrum. Measured 14C specific activity values in the samples varied from 130-700 kBq/g in the RBMK-1500 irradiated samples and from 3-12.5 Bq/g in the LVR-15 irradiated graphite samples. This corresponds to 15±4 - 80±10 ppm impurity of 14N in various graphite samples of RBMK reactor.

Activation of reactor graphite thermal conversion process with copper acetate

2021 ◽  
Author(s):  
Kirill B. Larionov ◽  
Albert Zh. Kaltaev ◽  
Vladimir E. Gubin ◽  
Andrey V. Zenkov
Keyword(s):  
Copper Acetate ◽  
Thermal Conversion ◽  
Conversion Process ◽  
Reactor Graphite

System for monitoring the energy distribution in the RBMK reactor

1973 ◽  
Vol 34 (5) ◽  
pp. 417-420
Author(s):  
I. Ya. Emel'yanov ◽  
L. V. Konstantinov ◽  
V. V. Postnikov ◽  
V. K. Denisov ◽  
V. Ya. Gurovich
Keyword(s):  
Energy Distribution ◽  
Rbmk Reactor

scholarly journals Review of reactor graphite distortion problems

1962 ◽  
Author(s):  
K.D. Coughren ◽  
F.J. Kempf ◽  
C.A. Munro
Keyword(s):  
Reactor Graphite

Waste Reduction by Re-Use of Low Activated Material

2009 ◽  
Author(s):  
Ulrich Ehrlicher ◽  
Heinz Pauli
Keyword(s):  
Radioactive Waste ◽  
Radiation Protection ◽  
Waste Reduction ◽  
Steel Plates ◽  
Radioactive Material ◽  
Filling Material ◽  
Financial Benefit ◽  
Reactor Graphite ◽  
Legislative Framework ◽  
Paul Scherrer

A multidisciplinary institute, equipped with research reactors and accelerator-driven research installations produces and, in the case of PSI, collects radioactive waste on one hand and requires material, especially for shielding purpose, on the other hand. The legislative framework for radiation protection, financial reasons and limited storage capacity strongly force Paul Scherrer Institute and comparable facilities to minimize radioactive waste. Besides free release of inactive components, recycling and re-use of low-level radioactive material in controlled areas are the best means for waste minimization. The re-use of slightly activated steel plates as a shielding material and the recycling of irradiated reactor graphite as a filling material embedded in mortar may give examples and encouragement for similar activities. Besides the advantages for radiation protection, the financial benefit can be measured in millions of dollars.

Investigation of radiation creep of reactor graphite

Atomic Energy ◽  
2008 ◽  
Vol 105 (2) ◽  
pp. 104-109 ◽  
Author(s):  
A. V. Subbotin ◽  
A. S. Pokrovskii ◽  
D. V. Khar’kov
Keyword(s):  
Radiation Creep ◽  
Reactor Graphite

scholarly journals Influence of vacuumetric pressure on thermal properties of high-temperature radioactive graphite-nitrogen system

2021 ◽  
Vol 2119 (1) ◽  
pp. 012095
Author(s):  
M R Shavaleev ◽  
N M Barbin ◽  
D I Terentyev ◽  
S I Osipenko ◽  
D S Belkin
Keyword(s):  
Thermal Properties ◽  
High Temperature ◽  
Atmospheric Pressure ◽  
Thermodynamic Data ◽  
Nitrogen Atmosphere ◽  
Vacuum Pressure ◽  
Radioactive Graphite ◽  
Reactor Graphite ◽  
High Temperature Processing

Abstract To improve and specify the method proposed by the authors for high-temperature processing of reactor graphite in a nitrogen atmosphere, the thermodynamic data of the formed nitride compounds are supplemented and the system is calculated at a vacuum pressure of 0.5 atm. The data obtained are compared with the values at atmospheric pressure.

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