Impact of Workstations on Criticality Analyses at ABB Combustion Engineering
- ABB Combustion Engineering Nuclear Power, Inc., Windsor, CT (United States)
During 1991, ABB Combustion Engineering (ABB C-E) made the transition from a CDC Cyber 990 mainframe for nuclear criticality safety analyses to Hewlett Packard (HP)/Apollo workstations. The primary motivation for this change was improved economics of the workstation and maintaining state-of-the-art technology. The Cyber 990 utilized the NOS operating system with a 60-bit word size. The CPU memory size was limited to 131 100 words of directly addressable memory with an extended 250000 words available. The Apollo workstation environment at ABB consists of HP/Apollo-9000/400 series desktop units used by most application engineers, networked with HP/Apollo DN10000 platforms that use 32-bit word size and function as the computer servers and network administrative CPUS, providing a virtual memory system.
- Research Organization:
- ABB Combustion Engineering Nuclear Power, Inc., Windsor, CT (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- OSTI ID:
- 5769419
- Report Number(s):
- CONF-930601--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 68; ISSN 0003-018X; ISSN TANSAO
- Publisher:
- American Nuclear Society
- Country of Publication:
- United States
- Language:
- English
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Migration of nuclear criticality safety software from a mainfram to a workstation environment
Migration of Nuclear Criticality Safety Software from a Mainframe to a Workstation Environment
Related Subjects
420203* -- Engineering-- Handling Equipment & Procedures
663610 -- Neutron Physics-- (1992-)
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
ABB Combustion Engineering (ABB C-E)
BOLTZMANN EQUATION
CALCULATION METHODS
COMPUTERIZED SIMULATION
COMPUTERS
CRAY COMPUTERS
CRITICALITY
DIFFERENTIAL EQUATIONS
EQUATIONS
MONTE CARLO METHOD
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
NUMERICAL SOLUTION
Nuclear Criticality Safety Program (NCSP)
PARTIAL DIFFERENTIAL EQUATIONS
RADIATION TRANSPORT
SAFETY ANALYSIS
SIMULATION
Workstations