High-level radiation field analysis using Monte Carlo simulation in Kori Nuclear Power Pant unit 1
- 1. Hanyang Univ., Seoul (Korea, Republic of)
- 2. Ministry of Science and Technology, Seoul (Korea, Republic of)
Description
Radiation field analysis in nuclear power plant (NPP) was performed by using Monte Carlo simulation against whole containment building. In this work, the neutron energy spectra were calculated in the high-level radiation field of Kori Unit 1 in Korea, which is to be a basis of dose assessment for NPP workers. The Monte Carlo calculation was divided into two steps, neutron source term generation, and neutron energy spectrum calculation, to improve the calculation efficiency. The neutron energy spectra were, in this work, obtained at six points where the NPP workers should access. Even though the results are not compared with measurement data, it is noted that this approach can be employed for radiation field analysis. In the near future, a comparison between calculation results and measurement data will be carried out. (author)
Availability note (English)
Available from the Internet at URL https://www.tandfonline.com/doi/abs/10.1080/00223131.2004.10875652Additional details
Identifiers
Publishing Information
- Publisher
- Atomic Energy Society of Japan
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Proceedings of the 2nd ITRS international symposium on radiation safety and detection technology (ISORD-2)
- Imprint Pagination
- 545 p.
- Journal Page Range
- p. 90-92
Conference
- Title
- 2. ITRS international symposium on radiation safety and detection technology
- Acronym
- ISORD-2
- Dates
- 24-25 Jul 2003
- Place
- Sendai, Miyagi (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 51063547
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; EFFICIENCY; KORI-1 REACTOR; M CODES; MONTE CARLO METHOD; NEUTRON SPECTRA; RADIATION DOSE DISTRIBUTIONS; RADIATION DOSES; REACTOR VESSELS; SOURCE TERMS
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; CONTAINERS; DOSES; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SIMULATION; SPECTRA; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 7 refs., 6 figs.; This record replaces 36063968 Imprint:Published as Supplement 4 (March 2004) of Journal of Nuclear Science and Technology