Final Safety Analysis Report on the Brookhaven High Flux Beam Research Reactor

Final Safety Analysis Report on the Brookhaven High Flux Beam Research Reactor PDF Author: Joseph M. Hendrie
Publisher:
ISBN:
Category : Heavy water reactors
Languages : en
Pages : 0

Get Book Here

Book Description

Final Safety Analysis Report on the Brookhaven High Flux Beam Research Reactor

Final Safety Analysis Report on the Brookhaven High Flux Beam Research Reactor PDF Author: Joseph M. Hendrie
Publisher:
ISBN:
Category : Heavy water reactors
Languages : en
Pages : 0

Get Book Here

Book Description


Final Safety Analysis Report on the Brookhaven High Flux Beam Research Reactor

Final Safety Analysis Report on the Brookhaven High Flux Beam Research Reactor PDF Author: Joseph M. Hendrie
Publisher:
ISBN:
Category : Heavy water reactors
Languages : en
Pages :

Get Book Here

Book Description


Preliminary Hazards Summary Report on the Brookhaven High Flux Beam Research Reactor

Preliminary Hazards Summary Report on the Brookhaven High Flux Beam Research Reactor PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Get Book Here

Book Description
The High Flux Beam Reactor, HFBR, is cooled, moderated, and reflected by heavy water and designed to produce 40 Mw with a total epithermal flux of ~1.6 X 1015cm−2 sec−1 and a flector thermal maximum flux of 7 X 10/sup 14/ cm−2 sec−1, using a core formed by ETR plate-type fuel elements in a close-packed array. The hazards summary is given in terms of site description, reactor design, building design, plant operation, disposal of radioactive wastes and effluents, and safety analysis. (B.O.G.).

Safety Aspects of the Brookhaven High Flux Beam Reactor

Safety Aspects of the Brookhaven High Flux Beam Reactor PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 5

Get Book Here

Book Description


Safety Aspects of the Brookhaven High Flux Beam Reactor

Safety Aspects of the Brookhaven High Flux Beam Reactor PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 5

Get Book Here

Book Description
SAFETY DESIGN BASIS for the HFBR and Current Status.

Risk Analysis of Environmental Hazards at the High Flux Beam Reactor

Risk Analysis of Environmental Hazards at the High Flux Beam Reactor PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 6

Get Book Here

Book Description
In the late 1980s, a Level 1 internal event probabilistic risk assessment (PRA) was performed for the High-Flux Beam Reactor (HFBR), a US Department of Energy research reactor located at Brookhaven National Laboratory. Prior to the completion of that study, a level 1 PRA for external events was initiated, including environmental hazards such as fire, internal flooding, etc. Although this paper provides a brief summary of the risks from environmental hazards, emphasis will be placed on the methodology employed in utilizing industrial event databases for event frequency determination for the HFBR complex. Since the equipment in the HFBR is different from that of, say, a commercial nuclear power plant, the current approach is to categorize the industrial events according to the hazard initiators instead of categorizing by initiator location. But first a general overview of the analysis.

Nuclear Safety

Nuclear Safety PDF Author:
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 1750

Get Book Here

Book Description


Safety Issues at the DOE Test and Research Reactors

Safety Issues at the DOE Test and Research Reactors PDF Author: National Research Council (U.S.). Committee to Assess Safety and Technical Issues at DOE Reactors
Publisher: National Academies
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 164

Get Book Here

Book Description


Current and Prospective Safety Issues at the HFBR.

Current and Prospective Safety Issues at the HFBR. PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 6

Get Book Here

Book Description
The Brookhaven High Flux Beam Reactor (HFBR) was designed primarily to produce external neutron beams for experimental research. It is cooled, moderated and reflected by heavy water and uses MTR-ETR type fuel elements containing enriched uranium. The reactor power when operation began in 19965 was 40 MW, was raised to 60 MW in 1982 after a number of plant modifications, and operated at that level until 1989. Since that time safety questions have been raised which resulted in extended shutdowns and a reduction in operating power to 30 MW. This paper will discuss the principle safety issues, plans for their resolution and return to 60 MW operation. In addition, radiation embrittlement of the reactor vessel and thermal shield and its affect on the life of the facility will be briefly discussed.

Reactor Safety

Reactor Safety PDF Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 144

Get Book Here

Book Description