Published 1989 | Version v1
Book

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--.