Assessment of the radiation field from withdrawal of the internal components in a system integrated reactor
- 1. Dept. of Nuclear Engineering, Hanyang Univ., Seoul (Korea, Republic of)
- 2. Korea Inst. of Nuclear Safety, Daejon (Korea, Republic of)
Description
SMART (System-integrated Modular Advanced Reactor) is a small and medium size integrated reactor with 330 MWth power which has been developed in Korea. In the SMART, some of the components such as steam generator, flow mixing header assembly and flow skirt are installed inside the reactor vessel and near the core, which lead to their activation. The components will be withdrawn for maintenance, inspection, replacement or decommissioning, which causes radiation fields from them. In order to evaluate their activities and radiation fields, a computer-based simulation was performed using the MCNPX code. We calculated the dose rates by distance from the surface of the components to 5 m away and the variation of dose rates over time. Dose rates near the withdrawn components are extremely high and the dose rate is still extremely high after sufficient cooling time. Thus, approach to these components must be prohibited and all of works relevant with the withdrawn components must be performed by remote control system. (author)
Availability note (English)
Available from http://dx.doi.org/10.15669/pnst.3.44Additional details
Identifiers
- DOI
- 10.15669/pnst.3.44;
Publishing Information
- Journal Title
- Progress in Nuclear Science and Technology
- Journal Volume
- 3
- Journal Page Range
- p. 44-47
- ISSN
- 2185-4823
Conference
- Title
- 6. international symposium on radiation safety and detection technology
- Acronym
- ISORD-6
- Dates
- 12-14 Jul 2011
- Place
- Langkawi (Malaysia)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 49052934
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CHEMICAL COMPOSITION; COBALT 60; COMPUTER CODES; COMPUTERIZED SIMULATION; DOSE RATES; INCONEL 690; NUCLEAR REACTIONS; RADIOACTIVITY; REACTOR CORES; REACTOR VESSELS; SMALL MODULAR REACTORS; STAINLESS STEEL-304; STEAM GENERATORS; THERMAL NEUTRONS
- Descriptors DEC
- ALLOY-NI59CR30FE9; ALLOYS; AUSTENITIC STEELS; BARYONS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; BOILERS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; COBALT ISOTOPES; CONTAINERS; CORROSION RESISTANT ALLOYS; ELEMENTARY PARTICLES; FERMIONS; HADRONS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; INCONEL ALLOYS; INTERMEDIATE MASS NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; IRON ALLOYS; IRON BASE ALLOYS; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MATERIALS; MINUTES LIVING RADIOISOTOPES; NEUTRONS; NICKEL ALLOYS; NICKEL BASE ALLOYS; NUCLEI; NUCLEONS; ODD-ODD NUCLEI; RADIOISOTOPES; REACTOR COMPONENTS; REACTORS; SIMULATION; STAINLESS STEELS; STEEL-CR19NI10; STEELS; TITANIUM ADDITIONS; TITANIUM ALLOYS; TRANSITION ELEMENT ALLOYS; VAPOR GENERATORS; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 5 refs., 6 figs., 2 tabs.