MCNP neutron streaming investigations from the reactor core to regions outside the reactor pressure vessel for a Swiss PWR
- 1. National Cooperative for the Disposal of Radioactive Waste (Nagra), Wettingen (Switzerland)
- 2. Nuclear Energy Systems Lab, ETH Zurich, Zurich (Switzerland)
- 3. Kernkraftwerk Goesgen-Daeniken AG, Daeniken (Switzerland)
Description
The Swiss National Cooperative for the Disposal of Radioactive Waste, partly in collaboration with ETH Zurich and the Swiss NPP utilities, has developed MCNP NPP models for neutron activation analysis and NPP decommissioning studies. These models exhibit mainly rotational symmetry and are bound to the reactor pit/drywell area. In this paper, the PWR Goesgen model is chosen as a reference model for further investigation and extended to incorporate detailed reactor pressure vessel support structures, cooling pipes/penetrations and farther ex-reactor pressure vessel areas such as the adjacent steam generator or cooling pump compartment as well as the layout of the basin area above the reactor pressure vessel. The impact of these azimuthal asymmetries on the ex-reactor pressure vessel neutron distribution is quantified and the variance reduction methodology used is outlined. Finally, a description of the in-situ foil irradiation campaign initiated in collaboration with the Swiss NPP Goesgen for the purpose of future model validation is presented. (author)
Availability note (English)
Available from http://dx.doi.org/10.15669/pnst.4.481Additional details
Identifiers
- DOI
- 10.15669/pnst.4.481;
Publishing Information
- Journal Title
- Progress in Nuclear Science and Technology
- Journal Volume
- 4
- Journal Page Range
- p. 481-485
- ISSN
- 2185-4823
Conference
- Title
- 12. international conference on radiation shielding; RPSD-2012: 17. topical meeting of the Radiation Protection and Shielding Division of ANS
- Acronym
- ICRS-12
- Dates
- 2-7 Sep 2012
- Place
- Nara (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 49058828
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; GOESGEN REACTOR; MONTE CARLO METHOD; NEUTRON ACTIVATION ANALYSIS; NEUTRON FLUX; NEUTRONS; NUCLEAR POWER PLANTS; PIPES; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; RADIATION STREAMING; RADIOACTIVATION; REACTOR DECOMMISSIONING; SHIELDING; VALIDATION
- Descriptors DEC
- ACTIVATION ANALYSIS; BARYONS; CALCULATION METHODS; CHEMICAL ANALYSIS; CONTAINERS; COOLING SYSTEMS; DECOMMISSIONING; ELEMENTARY PARTICLES; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; NONDESTRUCTIVE ANALYSIS; NUCLEAR FACILITIES; NUCLEONS; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; RADIATION FLUX; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR LIFE CYCLE; REACTORS; SIMULATION; TESTING; THERMAL POWER PLANTS; THERMAL REACTORS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 refs., 8 figs.