Analysis of the proposed relocation of the neutron criticality clusters in the process buildings for the Portsmouth Gaseous Diffusion Plant
- Battelle, Columbus, OH (United States)
Radiation levels in Buildings X-326, X-330 and X-333 have been determined for the ANSI minimum accident of concern at both the current and the proposed locations of the criticality alum system neutron detectors. This was performed in order to evaluate whether or not the detectors could be lowered from their current positions and still respond to the minimum accident of concern. Relocating the detectors could reduce the potential for worker in injury when the approximately 90-pound alarms need to be removed for periodic maintenance. It could also decrease the incidence of battery failure from elevated temperatures which can exceed 160 degrees F. At the proposed 1-meter elevation the detectors would be surrounded by the cells containing the cascade equipment; therefore, the detectors would be less responsive to a criticality event. The results of this analysis indicate that the detectors could be lowered from their current height of 5 meters to a height of 1 meter and still respond to the minimum accident of concern. This analysis was performed using the MCNP monte carlo code with a source corresponding to a critical system of uranyl fluoride solutions of 1.2, 3.0, and 4.95 weight percent U-235 enrichment. The neutron dose rates were evaluated at positions of 69 meters and 100 meters radially outward from the source at 5 meter and 1 meter heights. All neutron detectors located in the three process buildings are located within 100 meters from any potential criticality. This report details the methodology used for this study, background on the data employed, and a comparison to a similar analysis performed in 1983.
- Research Organization:
- Martin Marietta Energy Systems, Inc., Piketon, OH (United States); Portsmouth Gaseous Diffusion Plant, OH (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC05-76OR00001
- OSTI ID:
- 10137997
- Report Number(s):
- POEF-SH-12; ON: DE94009234
- Resource Relation:
- Other Information: PBD: Jan 1994
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
42 ENGINEERING
PORTSMOUTH GASEOUS DIFFUSION PLANT
ALARM SYSTEMS
POSITIONING
NEUTRON DETECTORS
CRITICALITY
SAFETY ENGINEERING
MONTE CARLO METHOD
COMPUTERIZED SIMULATION
URANYL FLUORIDES
ENRICHED URANIUM
054000
050500
420203
HEALTH AND SAFETY
URANIUM ENRICHMENT
HANDLING EQUIPMENT AND PROCEDURES