NUCLEAR MERCHANT SHIP REACTOR SHIELD DESIGN SUMMARY REPORT

Technical Report · Sat Aug 01 04:00:00 EDT 1959

OSTI ID:4128153

Smith, W R; Turner, M A

The calculated source strengths of the principle radiations are presented: neutron, primary, and secondary gamma ; core-fission product build-up and decay; coolant activation; and activation of materials. The primary shield tank design is developed in terms of neutron, primary, and secondary gamma dose rate profiles along the radial center-line. The biological shield design is outlined in terms of reactor sources and coolant sources. The reactor sources are treated as surface sources having a cosine-squared angular distribution. After-shutdown shielding for maintenance of components and fuel-handling operations is calculated. Fission product decay and Co/sup 60/ activity in stainless steel are the dominant sources. The accidental release of fission products to the containment is considered. There are four appendixes: Appendix A tabulates the nuclear properties of the core, thermal neutron capture cross sections of the core materials, and the values of miscellaneous parameters that define the system; Appendix B shows the methods of calculating the source strengths; Appendix C summarizes the methods of calculating radiation attenuations and dose rates; Appendix D describes the procedure for calculating fission and corrosion product radioactivities in the primary coolant. (auth)

• Research Organization: Babcock and Wilcox Co. Atomic Energy Div., Lynchburg, Va.
• NSA Number: NSA-15-002327
• OSTI ID: 4128153
• Report Number(s): BAW-1144-1
• Country of Publication: United States
• Language: English

Related Subjects

ACCIDENTS
ACTIVATION
CAPTURE
COBALT 60
COOLANTS
CORROSION
CROSS SECTIONS
FISSION PRODUCTS
FUEL ELEMENTS
GAMMA RADIATION
MATHEMATICS
NEUTRONS
PLANNING
RADIATION SOURCES
RADIATIONS
RADIOACTIVITY
REACTOR CORE
REACTOR TECHNOLOGY
REACTORS
REMOTE HANDLING
SHIELDING
SHIPS
STAINLESS STEELS