Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

A METHOD FOR CALCULATING THE NEUTRON FLUX IN A SHUTDOWN REACTOR WITH A PHOTONEUTRON SOURCE (in Russian)

Journal Article · · At. Energ. (USSR)
OSTI ID:4718800
Subcritical neutron flux measurements in a shutdown reactor are rendered difficult by the radiation of the fission products; artificial neutron sources are used to increase the neutron flux to the level required by the instrumentation. In order to eliminate the expensive Po-Be sources the use of photoneutron sources containing Be or heavy water is considered, employing Na/sup 24/, Sb/sup 124/, etc. as the gamma source. The decay of the source after the shutdown of the reactor is compensated by its activation by thermal neutrons during the subsequent operation of the reactor. The negative reactivity thus introduced must be compensated by a ( gamma ,n) reaction. A method was developed for calculating photoneutron sources with a gamma source consisting of the fission fragments formed during the operation of the reactor. The method also allows the calculation of photoneutron sources using radioactive isotopes, taking the relative positions of the Be and gamma emitter into consideration. The neutron flux in the core is determined by solving the eigenfunctions of the reactor. From these the required reactor power level and Be concentration may be obtained. The validity of the formula was verified with the First Soviet Atomic Power Station. Before startup at the subcritical state DELTA k = 0.093 an 8 kg BeO rod was introduced in the central lattice, resulting in an increase of the flux by a factor of 2.3 to 2.5. The calculated and experimental values agreed with each other within 10%. (TTT)
Research Organization:
Originating Research Org. not identified
NSA Number:
NSA-17-026797
OSTI ID:
4718800
Journal Information:
At. Energ. (USSR), Journal Name: At. Energ. (USSR) Vol. Vol: 14
Country of Publication:
Country unknown/Code not available
Language:
Russian