Criticality safety analysis of a borated-concrete absorber
- 1. Power Reactor and Nuclear Fuel Development Corp., Tokai, Ibaraki (Japan)
- 2. Oak Ridge National Lab., TN (United States)
Description
Fuel cycle facilities use slab tanks to store fissile solutions, because these tanks have both a high volume-to-floor-space efficiency and an easily verifiable, criticality control (thickness). The results of preliminary criticality analyses using a validated computer code and cross-section library, indicate that a slab tank designed without a solid neutron absorber is not economical in view of process requirements (inventory) and space limitations (layout). A subsequent calculational study assessed the possible increase in the thickness of a single, isolated slab tank using a solid neutron absorber. Finally, an analysis was performed to evaluate the maximum slab thickness for an array of tank/absorbers. The result of these studies shows the potential for expansion of slab tank thickness
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (USA)
- ISBN
- 0-89448-142-2
- Imprint Title
- Proceedings of the international topical meeting on safety margins in criticality safety
- Imprint Pagination
- 375 p.
- Journal Page Range
- p. 240-245.
Conference
- Title
- International topical meeting on safety margins in criticality safety.
- Dates
- 26 Nov - 1 Dec 1989.
- Place
- San Francisco, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22077269
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; CONCRETES; CRITICALITY; NEUTRON ABSORBERS; RADIATION PROTECTION; TANKS; THICKNESS
- Descriptors DEC
- BUILDING MATERIALS; CONTAINERS; DIMENSIONS; MATERIALS
Optional Information
- Secondary number(s)
- CONF-891118--.