FAST NEUTRON LEAKAGE

Technical Report · Mon Feb 22 04:00:00 EST 1960

OSTI ID:4719542

Wagner, E

Studies were made to determine the fast-neutron leakage out of the top and bottom of the pressure vessel of the Experimental Gas Cooled Reactor. The maximum value of the neutron flux at the outside surface of the reflector at the ends of the core is approximately 0.6 of the same quantity in the radial direction. The maximum flux, above 1 Mev in energy, at the radial and axial outside surfaces of the reflector are, respectively: 2.0 x 10/sup 9/ n/cm/sup 2/ sec and 1.25 x 10/sup 9/ n/cm/sup 2/ sec. The maximum axial flux, above 1 Mev in energy, at the inside surface of the pressure vessel on the vertical axis of the core is approximately 1.0 x 10/sup 8/ neutron per cm/sup 2/ sec. This is much less than the maximum in the radial direction, which is approximately 1.5 x 10/ sup 9/ neutrons per cm/sup 2/ sec, so that fast-neutron radiation damage due to diffusion of neutrons out of the reactor will accumulate much faster on the radial portion than on the hemispherical top and bottom heads of the pressure vessel. The results calculated for the maximum radial flux are compared with results from a moments-method calculation. The moments method gives a higher flux value by a factor of 1.4. (auth)

• Research Organization: Allis-Chalmers Mfg. Co. Atomic Energy Div., Washington, D.C.
• NSA Number: NSA-17-017554
• OSTI ID: 4719542
• Report Number(s): TID-18106; EGCR-STUDY-II-105-2
• Country of Publication: United States
• Language: English

Related Subjects

DIFFERENTIAL EQUATIONS
DIFFUSION
EGCR
EQUATIONS
FAST NEUTRONS
GAS COOLANT
LOSSES
NEUTRON FLUX
NEUTRONS
POWER PLANTS
PRESSURE VESSELS
RADIATION EFFECTS
REACTOR CORE
REACTOR TECHNOLOGY
REACTORS
REFLECTORS