This is the second annual report of an experimental program for the investigation of the neutronics of benchmark mock-ups of LMFBR blankets. Work was devoted primarily to measurements on Blanket Mock-Up No. 2, a simulation of a typical large LMFBR radial blanket and its steel reflector. Activation traverses and neutron spectra were measured in the blanket; calculations of activities and spectra were made for comparison with the measured data. The heterogeneous self- shielding effect for $sup 238$U capture was found to be the most important factor affecting the comparison. Optimization and economic studies were made which indicate that the use of a high-albedo reflector material such as BeO or graphite may improve blanket neutronics and econ...
In fusion devices, such as European Demonstration Fusion Power Reactor (EU DEMO), primary neutrons c...
The ASTRID project (Advanced Sodium Technological Reactor for Industrial Demonstration) is a Generat...
The paper summarizes preliminary results of neutronic analysis of candidate ATF cladding materials t...
Work during the period was devoted primarily to a range of analytical/numerical investigations, incl...
"August 1983.""DOE/ET/37241-54."Includes bibliographical references (pages 49-58)Final summary repor...
Irradiation experiments on Mockup 5B have been completed. A series of comparative calculations are u...
Information is presented concerning benchmark calculations for reactivity coefficients; and neutroni...
While reactor programs change, shielding analysis methods are improved slowly. Version-V of ENDF/B p...
The neutron reflector is a general component in the nuclear reactor design. The original SMART react...
The neutron reflector is a general component in the nuclear reactor design. The original SMART react...
Argonne National Laboratory has the largest US program for the development of blanket technology. Th...
A new conceptual design of a fusion reactor blanket simulation facility has been developed. This des...
The paper presents the results of the efforts concerned with expanding the verification database and...
Mechanic solicitations induced by neutron and photon interactions have to be featured for components...
At Fusion Neutronics Source (FNS), we have done experiments with thermal-type breeding blanket mock-...
In fusion devices, such as European Demonstration Fusion Power Reactor (EU DEMO), primary neutrons c...
The ASTRID project (Advanced Sodium Technological Reactor for Industrial Demonstration) is a Generat...
The paper summarizes preliminary results of neutronic analysis of candidate ATF cladding materials t...
Work during the period was devoted primarily to a range of analytical/numerical investigations, incl...
"August 1983.""DOE/ET/37241-54."Includes bibliographical references (pages 49-58)Final summary repor...
Irradiation experiments on Mockup 5B have been completed. A series of comparative calculations are u...
Information is presented concerning benchmark calculations for reactivity coefficients; and neutroni...
While reactor programs change, shielding analysis methods are improved slowly. Version-V of ENDF/B p...
The neutron reflector is a general component in the nuclear reactor design. The original SMART react...
The neutron reflector is a general component in the nuclear reactor design. The original SMART react...
Argonne National Laboratory has the largest US program for the development of blanket technology. Th...
A new conceptual design of a fusion reactor blanket simulation facility has been developed. This des...
The paper presents the results of the efforts concerned with expanding the verification database and...
Mechanic solicitations induced by neutron and photon interactions have to be featured for components...
At Fusion Neutronics Source (FNS), we have done experiments with thermal-type breeding blanket mock-...
In fusion devices, such as European Demonstration Fusion Power Reactor (EU DEMO), primary neutrons c...
The ASTRID project (Advanced Sodium Technological Reactor for Industrial Demonstration) is a Generat...
The paper summarizes preliminary results of neutronic analysis of candidate ATF cladding materials t...