1. Date of download: 10/13/2017
Copyright © ASME. All rights reserved.
From: The Effect of Iron Cross-Section in Thermal Region on Neutron Transport in VVER-1000 Mock-Up in LR-0 Reactor
ASME J of Nuclear Rad Sci. 2016;3(1): doi: /
Figure Legend:
General view on the LR-0 reactor and mock-up core with barrel and baffle simulators

2. Date of download: 10/13/2017
Copyright © ASME. All rights reserved.
From: The Effect of Iron Cross-Section in Thermal Region on Neutron Transport in VVER-1000 Mock-Up in LR-0 Reactor
ASME J of Nuclear Rad Sci. 2016;3(1): doi: /
Figure Legend:
Top view of the experimental arrangement showing thermal neutron fluxes measuring points in the RPV simulator

3. Date of download: 10/13/2017
Copyright © ASME. All rights reserved.
From: The Effect of Iron Cross-Section in Thermal Region on Neutron Transport in VVER-1000 Mock-Up in LR-0 Reactor
ASME J of Nuclear Rad Sci. 2016;3(1): doi: /
Figure Legend:
Selected pins for power density measurement (red numbering) in the LR-0 reactor

4. Date of download: 10/13/2017
Copyright © ASME. All rights reserved.
From: The Effect of Iron Cross-Section in Thermal Region on Neutron Transport in VVER-1000 Mock-Up in LR-0 Reactor
ASME J of Nuclear Rad Sci. 2016;3(1): doi: /
Figure Legend:
C/E-1 comparison for fission density/s normalized per 10−9  A of monitor current in various nuclear data libraries. Gray lines correspond to plus or minus one sigma uncertainty

5. Date of download: 10/13/2017
Copyright © ASME. All rights reserved.
From: The Effect of Iron Cross-Section in Thermal Region on Neutron Transport in VVER-1000 Mock-Up in LR-0 Reactor
ASME J of Nuclear Rad Sci. 2016;3(1): doi: /
Figure Legend:
Relative comparison of pin power density in fuel assembly adjacent to the baffle of LR-0 mock-up calculated with ENDF-VII.0 and CENDL-3.1 libraries (baffle is situated behind the top row of pins). Spatial dimensions are given in centimetres

6. Date of download: 10/13/2017
Copyright © ASME. All rights reserved.
From: The Effect of Iron Cross-Section in Thermal Region on Neutron Transport in VVER-1000 Mock-Up in LR-0 Reactor
ASME J of Nuclear Rad Sci. 2016;3(1): doi: /
Figure Legend:
(a) Left panel illustrates the relative comparison of pin power density in LR-0 mock-up with the situation in which the baffle was replaced by the moderator; (b) right panel shows the comparison between LR-0 mock-up and case, where the influence of baffle is neglected (neutron importance was set to zero for baffle) in fuel assembly adjacent to the baffle of LR-0 mock-up. All calculations employ ENDF-VII.0 library. Spatial dimensions are given in centimetres