Impact of shield elements on the WWER-440 reactor pressure vessel activation
- 1. Nuclear Engineering Laboratory, Lithuanian Energy Institute, Breslaujos 3, 44403 Kaunas (Lithuania)
Description
Highlights: • Neutron flux and induced activities are estimated for RPV of WWER-440 reactor. • MCNP code and SCALE codes system are used for modelling. • Shield elements effect for RPV activation is demonstrated. - Abstract: The WWER-440 type nuclear reactor is one of the most common reactor types in the nuclear power plants (NPP) across Central and Eastern Europe. Most of the NPPs equipped with these reactors have reached or are approaching the end of their service lifetime and face decommissioning. Neutron activated components of these reactors (the largest being the reactor pressure vessel (RPV)) are the most hazardous radioactive waste arising during decommissioning. Some of these reactors were equipped with shield elements (dummy fuel assemblies) in order to reduce neutron flux affecting the RPV. Therefore, the induced activity of an RPV also depends on whether or not shield elements were used in a specific reactor. This paper presents the analysis of shield elements' influence on the induced activity of an RPV.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2019.03.008Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2019.03.008;
- PII
- S0306454919301331;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 130
- Journal Page Range
- p. 394-401
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51008087
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTERIZED SIMULATION; FUEL ASSEMBLIES; MONTE CARLO METHOD; NEUTRON ACTIVATION ANALYSIS; NEUTRON FLUX; PRESSURE VESSELS; RADIATION EFFECTS; REACTOR DECOMMISSIONING; SERVICE LIFE; SHIELDS; WWER TYPE REACTORS
- Descriptors DEC
- ACTIVATION ANALYSIS; CALCULATION METHODS; CHEMICAL ANALYSIS; CONTAINERS; DECOMMISSIONING; ENRICHED URANIUM REACTORS; LIFETIME; NONDESTRUCTIVE ANALYSIS; POWER REACTORS; PWR TYPE REACTORS; RADIATION FLUX; REACTOR LIFE CYCLE; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- © 2019 Elsevier Ltd. All rights reserved.