Determining axial fuel-rod power-density profiles from in-core neutron flux measurements

Author:

Kenneth Shultis J.

Publisher

Elsevier BV

Subject

Instrumentation,Nuclear and High Energy Physics

Reference11 articles.

1. MCNP, MCNP—A General Monte Carlo N-Particle Transport Code, vols. 1–3, LA-UR-03-1987, LA-CP-03-0245, LA-CP-03-0284, Los Alamos National Laboratory, 2003.

2. Introduction to Nuclear Reactor Theory;Lamarsh,1966

3. Development of micro-pocket fission detectors (MPFD) for near-core and in-core neutron flux monitoring

4. D.S. McGregor, J.K. Shultis, M.F. Ohmes, A.S.M. Sabbir Ahmed, R. Ortiz, K. Hoffert, Micro-pocket fission detectors (MPFD) for near-core and in-core neutron flux monitoring, Presented at the ANS Fourth International Topical Meeting NPIC & HMIT, Columbus, OH, September 2004, 19.

5. Numerical Recipes;Press,1992

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