Predictive evaluation of changes in the volumes of radioactive waste to be deeply dispositioned in activated reactor structures in the process of their storage after the final shutdown of the Belarusian NPP power units
https://doi.org/10.29235/1561-8358-2022-67-3-332-344
Abstract
This paper presents the results of computational studies of the amount of solid high-level and long-lived intermediate level radioactive waste (HLW and ILW-LL) generated during neutron activation of structural materials adjacent to the core of the VVER-1200 reactor of the Belarusian NPP, depending on the time after the final shutdown of the reactor. The assessment of the volumes of HLW and ILW-LL of activation origin, formed over 60 years of operation of the VVER-1200 reactor, was carried out on the basis of computational studies of the induced activity of structural and shielding materials using reactor and Monte Carlo program codes (SERPENT 2, TVS-M, DYN3D, MCU- PD). As a result of calculation studies, it was established that the masses and volumes of activated materials, according to the levels of pollution related to HLW and ILW‑LL, within 10 years after the final shutdown of the VVER-1200 reactor of the Belarusian NPP will be 273 tons and 43 m3 , respectively. In the interval of 30–70 years, the masses and volumes of activated materials of these categories of RW will amount to 262 t and 33 m3 , respectively. From 100 years to 200 years, the masses and volumes of activated materials of these categories of RW will be 118 t and 15 m3 , respectively. Within 10 years after the reactor shutdown, isotopes 55Fe (2.7 years), 60Co (5.27 years), 63Ni (96 years) will make the main contribution to the value of the integral specific activity of the materials of the structures of the fence, shaft, surfacing, reactor vessel, block of protective tubes (BPT), the space under the core, thermal insulation; after 10 years – 63Ni. The main contribution to the value of the integral specific activity of materials of absorbing elements (PEL) with Dy2TiO5 during the entire period of storage will be made by 63Ni.
About the Authors
M. L. ZhemzhurovBelarus
Mikhail L. Zhemzhurov – D. Sc. (Engineering), Associate Professor, Head of the Laboratory of Radiation and Chemical Research of the Environment
47/17, Prilesye village, Lugovoslobodskaya village, 223063, Minsk District, Minsk Region
G. M. Zhmura
Belarus
Georgy M. Zhmura – Senior Researcher of the Laboratory of Radiation and Chemical Research of the Environment
47/17, Prilesye village, Lugovoslobodskaya village, 223063, Minsk District, Minsk Region
I. E. Rubin
Belarus
Isaak E. Rubin – Senior Researcher of the Laboratory of Neutron Physics
47/17, Prilesye village, Lugovoslobodskaya village, 223063, Minsk District, Minsk Region
G. Z. Serebryany
Belarus
Grigory Z. Serebryany – Ph. D. (Engineering), Leading Researcher of the Laboratory of Radiation and Chemical Research of the Environment
47/17, Prilesye village, Lugovoslobodskaya village, 223063, Minsk District, Minsk Region
N. M. Dneprovskaya
Belarus
Nina M. Dneprovskaya – Researcher of the Laboratory
of Neutron Physics
47/17, Prilesye village, Lugovoslobodskaya village, 223063, Minsk District, Minsk Region
N. A. Tetereva
Belarus
Natalia A. Tetereva – Researcher of the Laboratory of Neutron Physics
47/17, Prilesye village, Lugovoslobodskaya village, 223063, Minsk District, Minsk Region
I. V. Rudenkov
Belarus
Ivanton V. Rudenkov – Junior Researcher of the Laboratory of Modeling of Supercomputer Technologies in Nuclear Physics and Power Engineering
47/17, Prilesye village, Lugovoslobodskaya village, 223063, Minsk District, Minsk Region
L. F. Babichev
Belarus
Leonid F. Babichev – Ph. D. (Physics and Mathematics), Associate Professor, Head of the Laboratory for Modeling Supercomputer Technologies in Nuclear Physics and Power Engineering
47/17, Prilesye village, Lugovoslobodskaya village, 223063, Minsk District, Minsk Region
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