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Measurements for the JASPER program Axial Shield Experiment

Technical Report ·
DOI:https://doi.org/10.2172/432814· OSTI ID:432814
; ;  [1]; ;  [2]
  1. Oak Ridge National Lab., TN (United States)
  2. Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan)
The Axial Shield Experiment was conducted at the Oak Ridge National Laboratory (ORNL) during 1990--1991 as part of the continuing series of eight experiments planned for the Japanese-American Shielding Program for Experimental Research (JASPER) program starting in 1986. The program is intended to provide support for the development of current designs proposed for advanced liquid metal reactor (LMR) system both in Japan and the United States. As in the previous two experiments, the same spectrum modifier was used to alter the Tower Shielding Reactor source spectrum to one representing the LMR neutron spectra directly above the core in the area of the fission-gas plenum. In one of the measurements the spectrum was further modified by the fission gas plenum. In all cases the modified spectrum was followed by combinations of seven hexagon assemblies that represented different coolant flow and shielding patterns within the assemblies. The varied configuration permitted not only a study of the different designs, but also allowed a comparison to be made of the relative neutron attenuation effectiveness of boron carbide and stainless steel in such designs. This experiment was the third in a series of eight experiments to be performed as part of a cooperative effort between the United States Department of Energy (US DOE) and the Japan Power Reactor and Nuclear Fuel Development Corporation (PNC). This experiment, as was the previous Radial Shield Attenuation and Fission Gas Plenum Experiments, intended to provide support for the development of advanced sodium-cooled reactors. 5 refs.
Research Organization:
Oak Ridge National Lab., TN (United States)
Sponsoring Organization:
USDOE Assistant Secretary for Nuclear Energy, Washington, DC (United States)
DOE Contract Number:
AC05-84OR21400
OSTI ID:
432814
Report Number(s):
ORNL/TM--11839; ON: DE97003416
Country of Publication:
United States
Language:
English