Shielding Calculations for the MERLIN Research Reactor; ABSCHIRMUNGSBERECHNUNG FUR DEN FORSCHUNGSREAKTOR MERLIN

Technical Report · Sat Sep 01 04:00:00 EDT 1962

OSTI ID:4756499

Schaffer, O

Dimensions of the reactor, determination of the macroscopic mass-removal cross section for concrete, fast and thermal neutron fluxes and gamma dose rates are discussed. Under very pessimistic assumptions the dose rate at the outer surface of the concrete shielding was calculated to the 0.6548 mrem/hr. Since the permissible tolerance dose rate amounts to 0.75 mrem/hr, it was concluded that the radial shielding of the Merlin is sufficient. (M.C.G.)

• Research Organization: Kernforschungsanlage, Julich, Germany
• NSA Number: NSA-17-007632
• OSTI ID: 4756499
• Report Number(s): JUL-67-RE
• Country of Publication: Germany
• Language: English

Related Subjects

ABSORPTION
CONCRETES
CONFIGURATION
CROSS SECTIONS
EQUATIONS
FAST NEUTRONS
GAMMA RADIATION
MERLIN
MERLIN-JUELICH
NEUTRON FLUX
NUMERICALS
RADIATION DOSES
RADIATION PROTECTION
REACTOR CORE
REACTOR SAFETY
REACTOR TECHNOLOGY
REACTORS
RESEARCH REACTORS
SHIELDING
SHIELDING MATERIALS
STANDARDS
SURFACES
THERMAL NEUTRONS
THICKNESS
WATER COOLANT
WATER MODERATOR