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Title: EFFECT OF RADIATION DAMAGE ON SM-1, SM-1A AND PM-2A REACTOR VESSELS

Abstract

The status of the SM-1, SM-lA, and PM-2A reactor vessels is discussed with regard to effect of irradiation on nil-ductility transition temperature and the associated problem of brittle fracture. The three vessels are reported not subject to brittle fractures at present because of restrictions placed on operation during startup and shutdown. At temperatures where brittle fracture could occur, stresses were limited to 18% of the yield strength of the vessel material. Vessel stresses were limited by controlling the primary systerm pressure, cooling and heating rates and core power level. (auth)

Authors:
; ; ; ; ; ;
Publication Date:
Research Org.:
Alco Products, Inc., SChenectady, N.Y.
OSTI Identifier:
4804896
Report Number(s):
APAE-107
NSA Number:
NSA-16-005753
DOE Contract Number:  
AT(30-1)-2639
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-62
Country of Publication:
United States
Language:
English
Subject:
METALS, CERAMICS, AND OTHER MATERIALS; BRITTLENESS; COOLING; DUCTILITY; ENERGY; FAILURES; HEATING; LEVELS; OPERATION; PM-2A; PRESSURE; RADIATION EFFECTS; REACTOR CORE; REACTORS; SHUTDOWN; SM-1; SM-1A; STARTUP; STRESSES; TEMPERATURE; TENSILE PROPERTIES; VELOCITY; VESSELS

Citation Formats

McLaughlin, D.W., Rowekamp, B.J., Chittum, R.A., Kelleman, R.W., Bobe, P.E., Clancy, E.F., and Coombe, J.R. EFFECT OF RADIATION DAMAGE ON SM-1, SM-1A AND PM-2A REACTOR VESSELS. United States: N. p., 1961. Web. doi:10.2172/4804896.
McLaughlin, D.W., Rowekamp, B.J., Chittum, R.A., Kelleman, R.W., Bobe, P.E., Clancy, E.F., & Coombe, J.R. EFFECT OF RADIATION DAMAGE ON SM-1, SM-1A AND PM-2A REACTOR VESSELS. United States. doi:10.2172/4804896.
McLaughlin, D.W., Rowekamp, B.J., Chittum, R.A., Kelleman, R.W., Bobe, P.E., Clancy, E.F., and Coombe, J.R. Sat . "EFFECT OF RADIATION DAMAGE ON SM-1, SM-1A AND PM-2A REACTOR VESSELS". United States. doi:10.2172/4804896. https://www.osti.gov/servlets/purl/4804896.
@article{osti_4804896,
title = {EFFECT OF RADIATION DAMAGE ON SM-1, SM-1A AND PM-2A REACTOR VESSELS},
author = {McLaughlin, D.W. and Rowekamp, B.J. and Chittum, R.A. and Kelleman, R.W. and Bobe, P.E. and Clancy, E.F. and Coombe, J.R.},
abstractNote = {The status of the SM-1, SM-lA, and PM-2A reactor vessels is discussed with regard to effect of irradiation on nil-ductility transition temperature and the associated problem of brittle fracture. The three vessels are reported not subject to brittle fractures at present because of restrictions placed on operation during startup and shutdown. At temperatures where brittle fracture could occur, stresses were limited to 18% of the yield strength of the vessel material. Vessel stresses were limited by controlling the primary systerm pressure, cooling and heating rates and core power level. (auth)},
doi = {10.2172/4804896},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1961},
month = {10}
}