The Influence of Burnup-Dependent Fission Spectra on Reactor Pressure Vessel Irradiation

Author:

Frej Wasastjerna1

Affiliation:

1. Nuclear Engineering Laboratory, Technical Research Centre of Finland P.O. Box208, SF-02151 ESPOO, Finland

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Reference8 articles.

1. Dynamic fracture analysis of a transverse wedge-loaded compact specimen

2. W. W. ENGLE, Jr. “A Users Manual for ANISN-A One Dimensional Discrete Ordinates Transport Code with Anisotropic Scattering”, ORNL K-1693, Oak Ridge National Laboratory (1973), RSIC Code Package CCC-254, Radiation Shielding Information Center.

3. R. W. ROUSSIN, “BUGLE-80-Coupled 47-Neutron, 20-Gamma-Ray,P3, Cross-Section Library for LWR Shielding Calculations”, RSIC Data Library Collection DLC-75, Radiation Shielding Information Center (1980).

4. J. R. LAMARSH, Introduction to Nuclear Reactor Theory, p. 97, Addison-Wesley, Reading, Massachusetts (1966).

5. F. WASASTJERNA, “PVIS-2-A Program Intended to Prepare a Fission Source for Pressure Vessel Irradiation Calculations with ANISN or DOT in Hexagonal Geometry”, RFD-17/89, Nuclear Engineering Laboratory, Technical Research Centre of Finland (1989).

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