The Dose Constraint Calculation of High Radioactivity Level Waste Canister Surface

Radiation dose and personnel protection are among the safety goals of geological disposal of high-level radioactive waste. The calculation of the dose field on the surface of the packaging container is of great significance for the research on the dose constraint value of the repository. This paper built model consulting the Sweden KBS-3 canister, the temporal and spatial distribution of the dose rate on canister surface was calculated by Monte Carlo method, the temporal and spatial distribution of radiation dose rate of the tunnel was obtained. The research results showed that the photon dose rate on canister surface was greater than the neutron dose rate by 4 to 6 orders of magnitude, and the dose value of repository tunnel within 100 thousand years was lower than the ICRP recommended dose limit value (0.3 mSv/a) by 5 orders of magnitude.

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Hanford waste treatment plant Immobilized High Level Waste (IHLW) canister radiation dose rate and radiolytic heat load analysis

10.2172/816301 ◽

2003 ◽

Author(s):

R M PIERSON

Keyword(s):

Radiation Dose ◽

Dose Rate ◽

Heat Load ◽

Waste Treatment ◽

Treatment Plant ◽

High Level Waste ◽

Radiation Dose Rate ◽

Waste Treatment Plant ◽

Load Analysis ◽

High Level

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EVALUATION OF RADIATION DOSE RATE OF RSG-GAS REACTOR

Urania Jurnal Ilmiah Daur Bahan Bakar Nuklir ◽

10.17146/urania.2018.24.3.4909 ◽

2018 ◽

Vol 24 (3) ◽

Author(s):

Amir Hamzah ◽

Hery Adrial ◽

Subiharto Subiharto

Keyword(s):

Radiation Dose ◽

Radiation Exposure ◽

Dose Rate ◽

Nuclear Reactor ◽

Area Measurement ◽

Radiation Dose Rate ◽

Safety Level ◽

Modeling And Analysis ◽

Dose Rates ◽

Limit Value

EVALUATION OF RADIATION DOSE RATE OF RSG-GAS REACTOR. The RSG-GAS reactor has been operated for 30 years. Since the nuclear reactor has been operated for a long time, aging process on its components may occur. One important parameter for maintaining the safety level of the RSG-GAS reactor is to maintain radiation exposure as low as possible, especially in the working area. The evaluation results should be able to demonstrate that the radiation exposure of the RSG-GAS is still safe for workers, communities and the surrounding environments. The purpose of this study is to evaluate radiation exposure in the working area to ensure that the operation of RSG-GAS is still safe for the next 10 years. The scope of this work is confirming the calculation results with the measured radiation dose in the RSG-GAS reactor working area. Measurement of radiation exposure is done by using the installed equipments at some points in the RSG-GAS working area and a portable radiation exposure measurement equipment. The calculations include performance of a modeling and analysis of dose rate distribution based on the composition and geometry data of RSG-GAS by using MCNP. The analysis results show that the maximum dose rate at Level 0 m working area of RSG-GAS reactor is 3.0 mSv/h with a deviation of 6%, which is relatively close to the measurement value. The evaluation results show that the dose rate in RSG-GAS working area is below the limit value established by the Nuclear Energy Regulatory Agency of Indonesia (BAPETEN) of 10 mSv/h (for the average effective dose of 20 mSv/year). Therefore, it is concluded that the dose rate in RSG-GAS working area is safe for personnel..Kata kunci: dose rates, RSG-GAS, radiation safety, MCNP.

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Numerical Simulation of Dispersion of Radionuclides Released from the Fukushima NPP and the Assessment of their Nuclear Impact

Applied Mechanics and Materials ◽

10.4028/www.scientific.net/amm.737.417 ◽

2015 ◽

Vol 737 ◽

pp. 417-421 ◽

Cited By ~ 2

Author(s):

Yue Guan ◽

Shi Fei Shen ◽

Hong Huang

Keyword(s):

Numerical Simulation ◽

Spatial Distribution ◽

Effective Dose ◽

Dose Rate ◽

Temporal And Spatial Distribution ◽

Rate Distribution ◽

Effective Dose Rate ◽

Temporal And Spatial ◽

Nuclear Crisis

A large number of radionuclides were discharged into oceans after the Fukushima nuclear crisis. In this paper, we employed ROMS to simulate the circulation of water around Japan. We evaluated the temporal and spatial distribution of radionuclides originated from Fukushima NPP, such as: Cs-137, Cs-134 and I-131. Then, we utilized MCNP 5 to assess the external nuclear impact of these nuclides in water and obtained the effective dose rate distribution in the coast water around Fukushima NPP.

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