THE U.S. EXPERIMENTAL PROGRAMME FOR FAST REACTOR PHYSICS

1967 ◽  
pp. 403-420
Author(s):  
R. AVERY ◽  
C.E. DICKERMAN ◽  
W.Y. KATO ◽  
J.K. LONG ◽  
A.B. SMITH ◽  
...  
Author(s):  
Pierre D’hondt ◽  
Peter Baeten ◽  
Leo Sannen ◽  
Daniel Marloye ◽  
Benoit Lance ◽  
...  

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.


2014 ◽  
Vol 2014 ◽  
pp. 1-9
Author(s):  
Peng Zhang ◽  
Kan Wang ◽  
Ganglin Yu

Super-Critical water-cooled Fast Reactor (SCFR) is a feasible option for the Gen-IV SCWR designs, in which much less moderator and thus coolant are needed for transferring the fission heat from the core compared with the traditional LWRs. The fast spectrum of SCFR is useful for fuel breeding and thorium utilization, which is then beneficial for enhancing the sustainability of the nuclear fuel cycle. A SCFR core is constructed in this work, with the aim of simplifying the mechanical structure and keeping negative coolant void reactivity during the whole core life. A core burnup simulation scheme based on Monte Carlo lattice homogenization is adopted in this study, and the reactor physics analysis has been performed with DU-MOX and Th-MOX fuel. The main issues discussed include the fuel conversion ratio and the coolant void reactivity. The analysis shows that thorium-based fuel can provide inherent safety for SCFR without use of blanket, which is favorable for the mechanical design of SCFR.


1984 ◽  
Vol 6 (3) ◽  
pp. 212-221 ◽  
Author(s):  
W. O. Harms ◽  
C. M. Purdy

1967 ◽  
pp. 615-630
Author(s):  
J.M. SIMMONS ◽  
E.R. ASTLEY ◽  
E.A. EVANS ◽  
J.H. KITTEL ◽  
D.A. MOSS ◽  
...  
Keyword(s):  

1967 ◽  
pp. 493-511
Author(s):  
H.H. HUMMEL ◽  
P. GREEBLER ◽  
W.B. LOEWENSTEIN ◽  
J.B. NIMS ◽  
A.B. REYNOLDS ◽  
...  

1968 ◽  
Vol 64 (3) ◽  
pp. 357
Author(s):  
E. Hellstrand
Keyword(s):  

Sign in / Sign up

Export Citation Format

Share Document