SCALE analysis of CLAB decay heat measurements for LWR spent fuel assemblies

Author:

Ilas Germina,Gauld Ian C.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference17 articles.

1. DeHart, M.D., 1992. A discrete ordinates approximation to the neutron transport equation applied to generalized geometries. Ph.D. Dissertation, Texas A&M University.

2. DeHart, M.D., Ulses, A.P., 2006. Lattice physics capabilities of the SCALE code system using TRITON. In: CD Proceedings of the ANS Topical Meeting on Reactor Physics PHYSOR-2006.

3. Gauld, I.C., 2006. Validation of ORIGEN-S decay heat predictions for LOCA analysis. In: CD Proceedings of the ANS Topical Meeting on Reactor Physics PHYSOR-2006.

4. Gauld, I.C., Ilas, G., Murphy, B.D., Weber, C.F., 2006. Validation of SCALE 5 decay heat predictions for LWR spent nuclear fuel. Technical Report ORNL/TM-2006/13, Oak Ridge National Laboratory.

5. Guttman, I., Wilks, S.S., Hunter, J.S., 1971. Introductory Engineering Statistics, Wiley Series in Probability and Mathematical Statistics – Applied. John Wiley & Sons.

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