A STUDY OF THE PRIMARY SHIELD FOR THE PRDC REACTOR
Temperature distributions, irradiation effects, stacking arrangements, voidage, and economics for the borated-graphite shield of the PRDC reactor were investigated. Of the shield systems considered, four are reported here. System 1 contalns 30 in. of 1% borated graphite, with either ordinary graphite or a cement as a filler for the remaindcr of the volume. The maximum temperature at the flex plates in this system was calculated to be 5OO deg F. Systems 2 and 3 consist of 2 in. of 5% borated graphite near the core vessel and 1/2 in. of Boral at the primary-shield tank. A filler material of carbon blocks is used in System 2 and graphite in System 3. The calculated maximum temperatures were 700 deg F and 35O deg F, respectively. System 4 consists of a laminated structure of Boral and graphite near the primary-shield tank and carbon-block filler. It was calculated to have a maximum temperature of 600 deg F at the flex plates. The maximum temperature at the flex plates recommended by APDA is 500 deg F. Energy storage and radiation damage were found to be within permissible limits in all four systems. However, these conclusions are based on experimental data from the Hanford reactor in which the neutron-energy spectrum differs considerably from the PRDC spectrum. A porosity of less than 740 cu ft is required in order that a sodium leak from the core vessel does not expose the core. The voidages in any of the systems mentioned above is about 400 cu ft excluding absorption effects. these are believed to be small. The systems coataining Boral were found to be less expensive than the ones using only borated graphite. Over-all material costs range between 0,000 for Boral systems and 0,000 for borated- graphite systems. (auth)
- Research Organization:
- Battelle Memorial Inst., Columbus, Ohio
- NSA Number:
- NSA-12-012863
- OSTI ID:
- 4334699
- Report Number(s):
- BMI-APDA-622
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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