ANALYSIS OF NEUTRON-EMBRITTLEMENT AND FLUX-DENSITY CONSIDERATIONS OF THE ARMY SM-1 REACTOR PRESSURE VESSEL,
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 n/sq.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)
Document Details
- Document Type
- Technical Report
- Publication Date
- Jun 22, 1970
- Accession Number
- AD0709898
Entities
People
- Charles Z. Serpan Jr.
Organizations
- United States Naval Research Laboratory