### Abstract

The multiple collision technique as applied to the monoenergetic time-dependent neutron transport equation for pulsed plan source emission in an infinite medium is used to obtain the flux due to a pulsed point source in the same medium. This result is then integrated to determine the flux due to the corresponding pulsed line source problem. The semi-infinite albedo problem is also shown to be solvable using the multiple collision approach. A generalization to include delayed neutrons follows directly from the multiple collision treatment, as does an equivalence between a monoenergetic time-dependent problem and a particular stationary slowing down problem in infinite geometry. Results are tabulated and comparisons are made to provide benchmark solutions to the fundamental time-dependent transport problems considered and thus bridge the gap between theory and practice.

Original language | English (US) |
---|---|

Pages (from-to) | 317-331 |

Number of pages | 15 |

Journal | Nuclear Science and Engineering |

Volume | 64 |

Issue number | 2 |

State | Published - Oct 1977 |

Externally published | Yes |

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### ASJC Scopus subject areas

- Nuclear Energy and Engineering

### Cite this

*Nuclear Science and Engineering*,

*64*(2), 317-331.

**GENERATION OF TIME-DEPENDENT NEUTRON TRANSPORT SOLUTIONS IN INFINITE MEDIA.** / Ganapol, Barry D; McKenty, P. W.; Peddicord, K. L.

Research output: Contribution to journal › Article

*Nuclear Science and Engineering*, vol. 64, no. 2, pp. 317-331.

}

TY - JOUR

T1 - GENERATION OF TIME-DEPENDENT NEUTRON TRANSPORT SOLUTIONS IN INFINITE MEDIA.

AU - Ganapol, Barry D

AU - McKenty, P. W.

AU - Peddicord, K. L.

PY - 1977/10

Y1 - 1977/10

N2 - The multiple collision technique as applied to the monoenergetic time-dependent neutron transport equation for pulsed plan source emission in an infinite medium is used to obtain the flux due to a pulsed point source in the same medium. This result is then integrated to determine the flux due to the corresponding pulsed line source problem. The semi-infinite albedo problem is also shown to be solvable using the multiple collision approach. A generalization to include delayed neutrons follows directly from the multiple collision treatment, as does an equivalence between a monoenergetic time-dependent problem and a particular stationary slowing down problem in infinite geometry. Results are tabulated and comparisons are made to provide benchmark solutions to the fundamental time-dependent transport problems considered and thus bridge the gap between theory and practice.

AB - The multiple collision technique as applied to the monoenergetic time-dependent neutron transport equation for pulsed plan source emission in an infinite medium is used to obtain the flux due to a pulsed point source in the same medium. This result is then integrated to determine the flux due to the corresponding pulsed line source problem. The semi-infinite albedo problem is also shown to be solvable using the multiple collision approach. A generalization to include delayed neutrons follows directly from the multiple collision treatment, as does an equivalence between a monoenergetic time-dependent problem and a particular stationary slowing down problem in infinite geometry. Results are tabulated and comparisons are made to provide benchmark solutions to the fundamental time-dependent transport problems considered and thus bridge the gap between theory and practice.

UR - http://www.scopus.com/inward/record.url?scp=0017546403&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=0017546403&partnerID=8YFLogxK

M3 - Article

AN - SCOPUS:0017546403

VL - 64

SP - 317

EP - 331

JO - Nuclear Science and Engineering

JF - Nuclear Science and Engineering

SN - 0029-5639

IS - 2

ER -