Multiplication of fission neutrons in beryllium oxide

Zhezherun, I.F.

doi:10.1007/bf01115914

Cited by 2 publications

(1 citation statement)

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“…According to a 1959 calculation [30], beryllium moderator increases the number of neutrons by 5.1% to 7.9%. According to a 1963 Soviet calculation [31], number of neutrons is increased by 10% in beryllium and 8% in beryllium oxide. In our calculations, the number of neutrons is increased by 9% to 11%.…”

Section: Neutron Multiplication By Berylliummentioning

confidence: 99%

Gas Core Reactors for Deep Space Propulsion

Shubov

2021

Preprint

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The operation of a nuclear power station powering Deep Space transport is presented in the paper. The power station consists of a Gas Core Reactor (GCR) with magnetohydrodynamic (MHD) generator. A new model of gas core reactor which has advantages by comparison with known models is suggested. It is shown that 200 ton system would generate 200 MW electricity. The gas core reactor consists of a spherical cavity of 1 m to 1.5 m radius surrounded by a 50 cm thick liquid beryllium reflector within molybdenum-92 container. The fuel consists of 235 UF 4 , KF, and K. It is demonstrated that such power station will work for gaseous fuel pressures of 50 atm to 100 atm. The Monte-Carlo simulations describing paths of thousands of neutrons are performed. These simulations yield neutronic results, i.e. the fractions of neutrons causing fission, being absorbed by moderator, and escaping the reactor. From this information one can calculate minimum needed pressure inside the reactor, the reactor size, and moderator thickness. The conductivity of superheated fuel depending on temperature and pressure is also calculated. It is concluded that space propulsion is the best use of uranium resources.

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Section: Neutron Multiplication By Berylliummentioning

confidence: 99%