APPLICATION OF PHILADELPHIA ELECTRIC COMPANY FOR CONSTRUCTION PERMIT AND CLASS 104 LICENSE. PEACH BOTTOM ATOMIC POWER STATION. PART A. GENERAL INFORMATION. PART B. PRELIMINARY HAZARDS SUMMARY REPORT. VOLUME I. PLANT DESCRIPTION AND SAFEGUARDS ANALYSIS. VOLUME II. SITE AND ENVIRONMENTAL INFORMATION
Technical Report
·
OSTI ID:4111703
The reactor system is of the solid fuel homogeneous type, employing graphite as moderator and helium as coolant. The fuel and fertile material (Th/ sup 232/) are in the form of carbides dispersed in the moderator. The design outlet gas temperature from the reactor will be l380 deg F at 350 psia with steam conditions of 1000 deg F at l450 psi. The plant will produce 40 Mw(e). The nuclear steam supply system, conventional equipment, containment, plant operation, radioactive effluents, and safety analysis are discussed. Radioactive inventories, site description, meteorology, hydrology, and geology are given. (W.D.M.)
- Research Organization:
- Philadelphia Electric Co.
- NSA Number:
- NSA-15-005815
- OSTI ID:
- 4111703
- Report Number(s):
- NP-9115
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-61
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
Similar Records
APPLICATION FOR USAEC LICENSES BY FLORIDA WEST COAST NUCLEAR GROUP. PART A. GENERAL INFORMATION. 40P. PART B. PRELIMINARY HAZARDS SUMMARY REPORT--VOLUME 1. CHARACTERISTICS OF SITE AND ENVIRONMENT. 71p. VOLUME 2. DESCRIPTION OF REACTOR AND PLANT. 181p. VOLUME 3. HAZARDS EVALUATION
HTGR TO HAVE CARBON-STEEL VESSEL. Completion of Peach Bottom estimated for March 1964, Steam conditions of 40-Mw unit to be 1,450 psi, 1,000 F
AN EVALUATION OF REACTOR CONCEPTS FOR USE AS SEPARATE STEAM SUPER-HEATERS
Technical Report
·
Tue Dec 01 00:00:00 EST 1959
·
OSTI ID:4111703
HTGR TO HAVE CARBON-STEEL VESSEL. Completion of Peach Bottom estimated for March 1964, Steam conditions of 40-Mw unit to be 1,450 psi, 1,000 F
Journal Article
·
Fri Dec 01 00:00:00 EST 1961
· Elec. World
·
OSTI ID:4111703
AN EVALUATION OF REACTOR CONCEPTS FOR USE AS SEPARATE STEAM SUPER-HEATERS
Technical Report
·
Sun Oct 01 00:00:00 EDT 1961
·
OSTI ID:4111703
+4 more
Related Subjects
REACTOR TECHNOLOGY
ACTIVATION
BREEDING
CARBIDES
CONTAMINATION
DISPERSIONS
FERTILE MATERIALS
FISSION PRODUCTS
FUELS
GAS COOLANT
GASES
GEOLOGY
GRAPHITE MODERATOR
GROUND WATER
HELIUM
HOMOGENEOUS REACTORS
LEAKS
METEOROLOGY
MODERATORS
POWER PLANTS
PRESSURE
REACTORS
SAFETY
SOLIDS
STEAM
TEMPERATURE
THORIUM 232
VESSELS
ACTIVATION
BREEDING
CARBIDES
CONTAMINATION
DISPERSIONS
FERTILE MATERIALS
FISSION PRODUCTS
FUELS
GAS COOLANT
GASES
GEOLOGY
GRAPHITE MODERATOR
GROUND WATER
HELIUM
HOMOGENEOUS REACTORS
LEAKS
METEOROLOGY
MODERATORS
POWER PLANTS
PRESSURE
REACTORS
SAFETY
SOLIDS
STEAM
TEMPERATURE
THORIUM 232
VESSELS