JASPER [Japanese-American Shielding Program of Experimental Research], USDOE/PNC shielding research program: Analysis of the JASPER fission gas plenum experiment

Technical Report · Tue May 01 00:00:00 EDT 1990

DOI:https://doi.org/10.2172/432810· OSTI ID:432810

Slater, C O

The results of the analysis of the Fission Gas Plenum Experiment are presented. This experiment is the second in a series of several experiments comprising a joint US DOE-Japan PNC Shielding Research Program (JASPER). The four Fission Gas Plenum Experiment configurations, designed for the measurement of neutron streaming through the fission gas plenum region, were analyzed using Monte Carlo and two-dimensional discrete ordinated methods. Calculated results compared well with measured results in many cases, although results were consistently underpredicted for the shorter plenum configurations. Like the measured data, the calculated results indicated no significant streaming when results from the heterogeneous mockups were compared to those from the homogeneous mockups. An explanation is given as to why little streaming was observed. The Hornyak button dose rates were overpredicted because of a normalization problem with the response function but yielded horizontal traverse curves whose shapes agreed well with the measured shapes to the same extent as did those for the other integral detectors. 16 refs., 16 figs., 4 tabs.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE Assistant Secretary for Nuclear Energy, Washington, DC (United States)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 432810
• Report Number(s): ORNL/TM-10681; ON: DE97003417
• Resource Relation: Other Information: PBD: May 1990
• Country of Publication: United States
• Language: English

Related Subjects

21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
22 NUCLEAR REACTOR TECHNOLOGY
LMFBR TYPE REACTORS
SHIELDING
PNC
US DOE
NEUTRON FLUX
DOSE RATES
FISSION PRODUCTS
COORDINATED RESEARCH PROGRAMS
FUEL ELEMENTS
BENCHMARKS
COMPUTER CALCULATIONS
D CODES
M CODES
G CODES
B CODES
V CODES
NEUTRON SPECTRA
EXPERIMENTAL DATA
REACTOR SAFETY