Infinite slab-shield dose calculations

Conference · Sun Jan 01 00:00:00 EST 1989

OSTI ID:5639969

Russell, G J

I calculated neutron and gamma-ray equivalent doses leaking through a variety of infinite (laminate) slab-shields. In the shield computations, I used, as the incident neutron spectrum, the leakage spectrum (<20 MeV) calculated for the LANSCE tungsten production target at 90{degree} to the target axis. The shield thickness was fixed at 60 cm. The results of the shield calculations show a minimum in the total leakage equivalent dose if the shield is 40-45 cm of iron followed by 20-15 cm of borated (5% B) polyethylene. High-performance shields can be attained by using multiple laminations. The calculated dose at the shield surface is very dependent on shield material. 4 refs., 4 figs., 1 tab.

• Research Organization: Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
• Sponsoring Organization: DOE/ER
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 5639969
• Report Number(s): LA-UR-89-3303; CONF-8810182-33; ON: DE90001826; TRN: 89-026478
• Resource Relation: Conference: International collaboration on advanced neutron sources (ICANS), Los Alamos, NM (USA), 3-7 Oct 1988
• Country of Publication: United States
• Language: English

Related Subjects

73 NUCLEAR PHYSICS AND RADIATION PHYSICS
RADIATION DOSES
CALCULATION METHODS
SHIELDING
NEUTRON TRANSPORT
DOSE RATES
GAMMA TRANSPORT THEORY
NEUTRON FLUENCE
NEUTRON LEAKAGE
PERFORMANCE
PHOTON TRANSPORT
DOSES
NEUTRAL-PARTICLE TRANSPORT
RADIATION TRANSPORT
TRANSPORT THEORY
654001* - Radiation &amp; Shielding Physics- Radiation Physics
Shielding Calculations &amp; Experiments
654003 - Radiation &amp; Shielding Physics- Neutron Interactions with Matter