SODIUM AS A SHIELD COMPONENT FOR FAST REACTORS
Technical Report
·
OSTI ID:4819748
A program has been conducted to evaluate the accuracy of calculation methods in sodium shields. Calculations using Monte Carlo, S {sub n}, and moments method solutions to the Boltzmann equation were performed. These results were compared with mesurements of slab geometry shield mockups. The fast neutron measurements were in good agreement with calculations, but at intermediate and thermal energies, the measurements showed less attenuation than predicted by the calculations. (auth)
- Research Organization:
- Atomics International, Canoga Park, CA (United States); Battelle-Northwest, Richland, WA (United States). Pacific Northwest Lab.
- Sponsoring Organization:
- British Nuclear Energy Society; The Insitute of Physics; The Physical Society
- NSA Number:
- NSA-23-013460
- OSTI ID:
- 4819748
- Report Number(s):
- AERE-R--5773(Vol.2); CONF-670932--(Vol.2)
- Country of Publication:
- United Kingdom
- Language:
- English
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Related Subjects
ATTENUATION
DIAGRAMS
ENERGY
FAST REACTORS
LIQUID METAL COOLANT
LOSSES
N38130* --Power Reactor Development--Shielding
NEUTRONS
NEUTRONS/attenuation by sodium in fast reactor shielding
(E/T)
NUMERICALS
REACTORS
REACTORS
FAST/shielding for
neutron attenuation properties of sodium as
(E/T)
REACTORS
LIQUID METAL-COOLED/shielding for
neutron attenuation properties of sodium as
(E/T)
SHIELDING MATERIALS
SODIUM
SODIUM/shielding properties in fast reactors
analysis of neutron
(E/T)
TABLES
DIAGRAMS
ENERGY
FAST REACTORS
LIQUID METAL COOLANT
LOSSES
N38130* --Power Reactor Development--Shielding
NEUTRONS
NEUTRONS/attenuation by sodium in fast reactor shielding
(E/T)
NUMERICALS
REACTORS
REACTORS
FAST/shielding for
neutron attenuation properties of sodium as
(E/T)
REACTORS
LIQUID METAL-COOLED/shielding for
neutron attenuation properties of sodium as
(E/T)
SHIELDING MATERIALS
SODIUM
SODIUM/shielding properties in fast reactors
analysis of neutron
(E/T)
TABLES