Radionuclide inventory analysis of the FLEXBLUE small modular reactor

Abstract Airborne laser scanning (also known as light detection and ranging or LIDAR) data were used to estimate three fundamental forest stand condition classes (forest stand size, land cover type, and canopy closure) at 32 Forest Inventory Analysis (FIA) plots distributed over the Kenai Peninsula of Alaska. Individual tree crown segment attributes (height, area, and species type) were derived from the three-dimensional LIDAR point cloud, LIDAR-based canopy height models, and LIDAR return intensity information. The LIDAR-based crown segment and canopy cover information was then used to estimate condition classes at each 10-m grid cell on a 300 × 300-m area surrounding each FIA plot. A quantitative comparison of the LIDAR- and field-based condition classifications at the subplot centers indicates that LIDAR has potential as a useful sampling tool in an operational forest inventory program.

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Prediction of the radionuclide inventory in the European Spallation Source target using FLUKA

Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms ◽

10.1016/j.nimb.2020.03.013 ◽

2020 ◽

Vol 471 ◽

pp. 24-32 ◽

Cited By ~ 1

Author(s):

Vytenis Barkauskas ◽

Kristina Stenström

Keyword(s):

Spallation Source ◽

Radionuclide Inventory

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Study on Typical Initial Event of ATWS for Small Modular Reactor

Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues ◽

10.1115/icone24-61166 ◽

2016 ◽

Author(s):

Zhang Dan ◽

Ran Xu ◽

Qiu Zhifang ◽

Zhou Ke ◽

Feng Li

Keyword(s):

Optimum Design ◽

Safety Analysis ◽

Accident Analysis ◽

Pressurized Water ◽

Control Rod ◽

Reactor Coolant ◽

Initial Event ◽

Small Modular Reactor ◽

Activation System

The method for ATWS (anticipated transient without scram) analysis was completely developed for commercial pressurized water (PWR) reactor plants, especially for selecting of typical initial events. For accident analysis of ATWS, it is different between PWR and small modular reactor (SMR), as different structures and characters, and it is necessary to study the typical initial events for these reactors. Based on the standard of PWR, the demanding for ATWS analysis was studied and the consequences for typical anticipated transient was calculated using RELAP5/MOD3.2 code, “maintain reactor coolant pressure boundary integrity” was selected as limiting criterion. The results shows for SMR, anticipated transient with the most serious consequence for ATWS are loss of offsite power and inadvertent control rod withdraw event, this conclusion will support to prepare the safety analysis report and optimum design of diversity activation system (DAS) for SMR.

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