PRIMARY COOLANT SYSTEM BLOWDOWN ACCIDENT FOR PEACH BOTTOM HTGR

Technical Report · Sat Dec 15 04:00:00 EST 1962

OSTI ID:4701330

Landon, J A; Skinner, M L

An investigation is made of helium depressurization in the Peach Bottom HTGR following large ruptures in the primary coolant system. Ruptures of a non- concentric duct near the steam generator and near the reactor vessel, as well as ruptures of the refueling nozzles in the top head of the reactor vessel, are assumed. Two different sizes of rupture openings are assumed at each location. Calculasions are performed with a Fortran code for the IBM 7090. The equations, Fortran program logic, Fortran listing, and sample computer printout are included. The results indicate that none of the ruptures investigated should cause permanent loss of flow (due to compressor damage) in both main coolant loops, or cause damage to both steam generators. Therefore, at least one compressor and its associated steam generator can always be available for postrupture forced- circulation cooling of the reactor. The complete shear and instantaneous removal of one of the largest fuel handling nozzles and plugs in the reactor vessel head is the only case that might lead to core lifting. The maximum height of core lifting is about 0.8 in. As a large concrete missile shield is located above the refueling nozzles, and prevents the nozzles and plugs from moving more than a fraction of an inch, the large opening assumed is impossible to attain. Therefore, levitation is considered an incredible'' accident. (auth)

• Research Organization: General Atomic Div. General Dynamics Corp., San Diego, Calif.
• NSA Number: NSA-17-029787
• OSTI ID: 4701330
• Report Number(s): GAMD-2605(Rev.2)
• Country of Publication: United States
• Language: English

Related Subjects

ACCIDENTS
COMPRESSORS
COMPUTERS
COOLANT LOOPS
EQUATIONS
FORTRAN
GENERATORS
HELIUM
HTGR
IBM 7090
MOTION
POWER PLANTS
PRESSURE
PROGRAMMING
REACTOR CORE
REACTOR TECHNOLOGY
SAFETY
SHIELDING
STEAM
VESSELS