Modelling of the shielding capabilities of the existing solid radioactive waste storages at Ignalina NPP
Creators
- 1. Lithuanian Energy Inst., Breslaujos 3, LT-44403 Kaunas (Lithuania)
Description
There is only one nuclear power plant in Lithuania - Ignalina NPP (INPP). The INPP operates two similar units with design electrical power of 1500 MW. The units were commissioned in 1983 and 1987 respectively. From the beginning of the INPP operation all generated solid radioactive waste was collected and stored at the Soviet type solid radwaste facility located at INPP site. The INPP solid radwaste storage facility consists of four buildings, namely building No. 155, No. 155/1, No. 157 and No. 157/1. The buildings of the INPP solid radwaste storage facility are reinforced concrete structures above ground. State Nuclear Safety Inspectorate (VATESI) has specified that particular safety analysis must be performed for existing radioactive waste storage facilities of the INPP. As part of the safety analysis, shielding capabilities of the walls and roofs of these buildings were analysed. This paper presents radiation shielding analysis of the buildings No. 157 and No. 157/1 that are still in operation. The buildings No. 155 and No. 155/1 are already filled up with the waste and no additional waste loading is expected. (authors)
Availability note (English)
Available from doi: http://dx.doi.org/10.1093/rpd/nci212Additional details
Identifiers
- DOI
- 10.1093/rpd/nci212;
Publishing Information
- Journal Title
- Radiation Protection Dosimetry
- Journal Volume
- 116
- Journal Issue
- 1-4
- Journal Page Range
- p. 423-427
- ISSN
- 0144-8420
Conference
- Title
- 10. International Conference on Radiation Shielding, and 13. ANS Topical Meeting on Radiation Protection and Shielding - ICRS-10/RPS 2004
- Dates
- 9-14 May 2004
- Place
- Funchal, Madeira Island (Portugal)
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- France
- INIS RN
- 44036003
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; IGNALINA-1 REACTOR; IGNALINA-2 REACTOR; MONTE CARLO METHOD; NEUTRONS; RADIATION MONITORING; RADIATION PROTECTION; RADIOACTIVE WASTE FACILITIES; RADIOACTIVE WASTE STORAGE; RADIOACTIVE WASTES; REINFORCED CONCRETE; SAFETY ANALYSIS; SHIELDING; SHIELDS; SOLID WASTES; STORAGE FACILITIES
- Descriptors DEC
- BARYONS; BUILDING MATERIALS; CALCULATION METHODS; COMPOSITE MATERIALS; CONCRETES; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; FERMIONS; GRAPHITE MODERATED REACTORS; HADRONS; LWGR TYPE REACTORS; MANAGEMENT; MATERIALS; MONITORING; NUCLEAR FACILITIES; NUCLEONS; POWER REACTORS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTE MANAGEMENT; REACTORS; REINFORCED MATERIALS; SIMULATION; STORAGE; THERMAL REACTORS; WASTE MANAGEMENT; WASTE STORAGE; WASTES; WATER COOLED REACTORS
Optional Information
- Notes
- 2 refs