ANALYSIS OF NEUTRON-EMBRITTLEMENT AND FLUX-DENSITY CONSIDERATIONS OF THE ARMY SM-1 REACTOR PRESSURE VESSEL,

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Abstract:

The Army SM-1 reactor has been evaluated with respect to the increase in transition temperature of the A212-B steel pressure vessel. Although steel from the heat forming the vessel is not available for irradiation-response behavior testing, the initial transition temperature of 40 deg F 4 deg C was determined from vessel steel. A relationship between increasing embrittlement for a 4-in.-thick plate of A212-B steel, representing the ASTM reference heat for this composition, and increasing neutron fluence was established for the irradiation temperature conditions of the SM-1 reactor. Combining with this the Army-imposed transition temperature limit for the SM-1 reactor vessel of 295 deg F 146 deg C results in a fluence value of 2.65 x 10 to the 19th power nsq.cm. 0.5 MeV for a lifetime vessel exposure. The neutron flux level for the vessel was established by extrapolating a core-region flux measurement using the results of a calculated neutron spectrum at the reactor vessel. Author

Author(s):
Serpan, Charles Z., Jr
Author Organization(s):
NAVAL RESEARCH LAB WASHINGTON D C
Pagination:
0024

Security Markings

DOCUMENT & CONTEXTUAL SUMMARY

Distribution:
Approved For Public Release

RECORD

Collection: TR
Identifying Numbers
Report Number(s):
NRL-7101
Project Number(s):
NRL-M01-14, USA-ERG-11-69
 Subject Terms
Communities of Interest:
Ground and Sea Platforms
Descriptor(s):
(*PRESSURIZED WATER REACTORS, PRESSURE VESSELS), (*STEEL, EMBRITTLEMENT), NEUTRON FLUX, DOSIMETERS, NEUTRON SPECTRUM, TEMPERATURE, ELECTRIC POWER PRODUCTION, NUCLEAR REACTORS, STATISTICAL ANALYSIS, TRANSITION TEMPERATURE, REACTOR SYSTEM COMPONENTS
Field(s)/Group(s):
Metallurgy and Metallography, Nuclear Power Plants and Fission Reactor Engineering
Keyword(s):
SM 1A REACTORS, FLUENCE, STEEL A 212
Report Date:
1970 Jun 22