Scenario for the severe beyond design basis accident at Kola NPP and its radiological consequences
Creators
- 1. Russian Research Centre Kurchatov Inst., Moscow (Russian Federation)
Description
Primary pipeline break LOCA with simultaneous loss of power in Kola-1 Reactor were assumed for the beyond-design-basis reference accident. Thermal-physical calculations for this reference accident were made using MELCOR code. Analysis of the reference accident indicates the following: 1) Fission products release occurs during the first hour of the accident. It includes a maximum of 3% of volatile products and 7% gases contained in the core. 2) The thyroid inhalation dose for 1 to 8 years old children at an early fase of the accident (10 days) exceeds the interventional level (500 mSv) specified in Russia for obligatory evacuation up to a distance of 24 km from the Kola NPP. For adults (5000 mSv) evacuation up to 3 km is specified. 4 refs., 2 tabs
Files
28041721.pdf
Files
(87.9 kB)
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Additional details
Publishing Information
- ISBN
- 82-90362-10-2
- Imprint Title
- Environmental radioactivity in the Arctic
- Imprint Pagination
- 427 p.
- Journal Page Range
- p. 373-376.
- Report number
- NEI-NO--747
Conference
- Title
- 2. international conference on environmental radioactivity in the Arctic.
- Dates
- 21-25 Aug 1995.
- Place
- Oslo (Norway).
INIS
- Country of Publication
- Norway
- Country of Input or Organization
- Norway
- INIS RN
- 28041721
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ENVIRONMENTAL IMPACTS; FISSION PRODUCT RELEASE; HUMAN POPULATIONS; KOLA-1 REACTOR; M CODES; RADIATION DOSES; RADIATION HAZARDS; REACTOR ACCIDENTS; RISK ASSESSMENT
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; HAZARDS; HEALTH HAZARDS; POPULATIONS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS