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ENGINEERING AND PHYSICAL CALCULATION OF BIOLOGICAL PROTECTION AGAINST RADIATIONS FROM NUCLEAR REACTORS (REVIEW ARTICLE) (in Russian)

Journal Article · · Inzhener.-Fiz. Zhur., Akad. Nauk Belorus. S.S.R.
OSTI ID:4827988
;
ABS>Creation of a light, compact, and economical biological shielding system assumes great importance as reactors are being used to a greater extent as a source of energy. The radiations encountered in an operating reactor are classified as primary radiations, originating directly from the fissioo process and including fission neutron ilunxes, instantaneous gamma radiation, delayed gamma radiation, and delayed neutrons. More than 50% of the fission neutrons undergo radiative capture, yielding gamma radiation, the energy of which may reach 10 Mev. In the case of closed-circuit heat transfer, the activation process mast be taken into account in the shielding design; for water-cooled reactors this effect is due to the reactions of the O isotopes, O/sup 16/(n,p)N/ sup 16/ and O/sup 17/(n,p)N/sup 17/. The fast neutron flux is often determined by the removal cross section; however, the spatial distribution and the energy spectrum of the intermediate lowenergy neutron flux cannot be determined by semiempirical methods and the kinetic equation must be solved. The theoretical principles of the attenuation of gamma radiation in the shielding materials are derived and the experimental confirmation of the equations is described. 51 references. (TTT)
Research Organization:
Originating Research Org. not identified
NSA Number:
NSA-16-021696
OSTI ID:
4827988
Journal Information:
Inzhener.-Fiz. Zhur., Akad. Nauk Belorus. S.S.R., Journal Name: Inzhener.-Fiz. Zhur., Akad. Nauk Belorus. S.S.R. Vol. Vol: 4: No. 12
Country of Publication:
Country unknown/Code not available
Language:
Russian

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Related Subjects

ABSORPTION
DISTRIBUTION
ENERGY RANGE
EQUATIONS
FAST NEUTRONS
GAMMA RADIATION
MEV RANGE
NEUTRONS
OXYGEN 16
PHYSICS
REACTORS
SHIELDING
SHIELDING MATERIALS
SLOWDOWN