Non-Markovian fission rate within the Kramers model

2015 ◽  
Vol 92 (2) ◽  
Author(s):  
S. V. Radionov ◽  
V. M. Kolomietz
Keyword(s):  
Fission Rate ◽  
Kramers Model

Correlations for Interaction Layer Growth in U-Mo/Al Dispersion Fuels

2017 ◽  
Vol 375 ◽  
pp. 29-39
Author(s):  
Boris A. Tarasov ◽  
Stepan N. Nikitin ◽  
Dmitry P. Shornikov ◽  
Maria S. Tarasova ◽  
Igor I. Konovalov
Keyword(s):  
Growth Rate ◽  
Growth Process ◽  
Aluminum Matrix ◽  
Layer Growth ◽  
Radiation Diffusion ◽  
Fission Rate ◽  
Interaction Layer ◽  
The Matrix ◽  
Mechanism And Kinetics ◽  
Kinetics Of

Paper presents the results of the growth rate of the interaction layer of uranium-molybdenum dispersed fuel in aluminum matrix and influence of silicon alloying on it. The growth process of amorphous interaction layer depends on the radiation diffusion which is proportional to the fission rate in the power of 1⁄4. The alloying of the matrix by silicon does not lead to a change in the mechanism and kinetics of the interaction layer growth, but only slows it down.

Measurement and analysis of thorium fission rate in a polyethylene shell with a D-T neutron source

2016 ◽  
Vol 113 ◽  
pp. 177-182 ◽  
Author(s):  
Lei Zheng ◽  
Yiwei Yang ◽  
Zhujun Liu ◽  
Rong Liu ◽  
Li Jiang ◽  
...  
Keyword(s):  
Neutron Source ◽  
Fission Rate ◽  
Measurement And Analysis

Numerical evaluation of the fractional Klein–Kramers model arising in molecular dynamics

2020 ◽  
pp. 109983
Author(s):  
O. Nikan ◽  
J.A. Tenreiro Machado ◽  
A. Golbabai ◽  
J. Rashidinia
Keyword(s):  
Molecular Dynamics ◽  
Numerical Evaluation ◽  
Kramers Model

The REBUS Experimental Programme for Burn-Up Credit

2004 ◽  
Author(s):  
Pierre D’hondt ◽  
Peter Baeten ◽  
Leo Sannen ◽  
Daniel Marloye ◽  
Benoit Lance ◽  
...  
Keyword(s):  
Water Level ◽  
Nuclear Research ◽  
Research Centre ◽  
Reactor Physics ◽  
Fission Rate ◽  
Mox Fuel ◽  
Experimental Programme ◽  
Fuel Bundle ◽  
International Programme ◽  
Good Agreement

An international programme called REBUS for the investigation of the burn-up credit has been initiated by the Belgian Nuclear Research Centre SCK-CEN and Belgonucle´aire with the support of EdF and IRSN from France and VGB, representing German nuclear utilities and NUPEC, representing the Japanese industry. Recently also ORNL from the U.S. joined the programme. The programme aims to establish a neutronic benchmark for reactor physics codes in order to qualify the codes for calculations of the burn-up credit. The benchmark exercise investigates the following fuel types with associated burn-up: reference fresh 3.3% enriched UO2 fuel, fresh commercial PWR UO2 fuel and irradiated commercial PWR UO2 fuel (54 GWd/tM), fresh PWR MOX fuel and irradiated PWR MOX fuel (20 GWd/tM). The experiments on the three configurations with fresh fuel have been completed. The experiments show a good agreement between calculation and experiments for the different measured parameters: critical water level, reactivity effect of the water level and fission-rate and flux distributions. In 2003 the irradiated BR3 MOX fuel bundle was loaded into the VENUS reactor and the associated experimental programme was carried out. The reactivity measurements in this configuration with irradiated fuel show a good agreement between experimental and preliminary calculated values.

Sign in / Sign up

Export Citation Format

Share Document