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U.S. Department of Energy
Office of Scientific and Technical Information

INTERIM REPORT ON REACTOR HAZARDS ASSOCIATED WITH THE PRESSURIZED WATER REACTOR PLANT AT SHIPPINGPORT, PENNSYLVANIA

Technical Report ·
OSTI ID:4302674
An analysis of zirconium-water reactions under conditions of accidental coolant loss is presented, including the production of hydrogen and a study of its explosive limits in the probable situation consequent to a major break in the PWR primary system. Situations of partially and fully uncovered reactor cores are examined, along with considerations of various possible undesirable water conditions resulting from improper reactor . operation. The power complex into which the PWR is to be integrated is discussed, including power demands, methods of control, and reliability. The applicable codes and regulations are discussed pointing out that questions concerning the non- conventional portions of the PWR plant were resolved. Meteorological data are discussed, and several charts are included. Primary loop materials are examined pointing out that ASME specifications are referred to except for piping which must conform to ASTM specifications and undergo ultrasonic tests. Materials of construction of the primary plant are examined, and it is concluded that all conditions leading to ferrous metal and alloy deficiencies are largely absent. An analytical expression for external gamma dosage around the reactor site from a sudden emission of radioactivity was calculated, along with calculation of the dosage in less severe situations of core meltdown with a breached container. Finally, some situations in which the primary coolant is discharged to the atmosphere are considered. (J.R.D.)
Research Organization:
Westinghouse Electric Corp. Bettis Plant, Pittsburgh
DOE Contract Number:
AT(11-1)-GEN-14
NSA Number:
NSA-12-017788
OSTI ID:
4302674
Report Number(s):
WAPD-SC-540(Vol.II(Del.))
Country of Publication:
United States
Language:
English