Author: R. J. BeeleyPublisher:
ISBN:
Category : Carbon
Languages : en
Pages : 68
Book Description
Operating Experience with the Sodium Reactor Experiment and Its Application to the Hallam Nuclear Power Facility
Author: R. J. BeeleyOPERATING EXPERIENCE WITH THE SODIUM REACTOR EXPERIMENT AND ITS APPLICATION TO THE HALLAM NUCLEAR POWER FACILITY.
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The Sodium Reactor Experiment (SRE) was constructed to demonstrate the feasibility of sodium-oooled graphitemoderated reactors for central station power. The operating experience of SRE has provided valuable data for the design of the Hallam Nuclear Power Facillty (HNPF) now under construction. Some of the difficulties found in the SRE, which HNPF will be designed to avoid, are the sodium-sodium intermediate heat exchanger (horizontal position in SRE gave trouble; a vertical position will be used in HNPF), sodium pumps, handling of broken fuel elements, and excessive thermal stresses due to inadequate coolant flow. Other features of HNPF include the addition of an activity monitoring system for the core cover gas, elimination of tetralin for auxiliary cooling of plant equipment, instrumentation of fuel elements, and addition of carbon traps in the primary sodium system. SRE operation has demonstrated unusual reactor stability and capability for rapid power changes. (D.L.C.).
First Sodium Reactor Experiment (SRE) Test of Hallam Nuclear Power Facility (HNPF) Control Materials
Author: S. O. ArnesonPublisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 36
Book Description
Engineering and Constructing the Hallam Nuclear Power Facility Reactor Structure
Author: J. E. MahlmeisterPublisher:
ISBN:
Category : Sodium graphite reactors
Languages : en
Pages : 72
Book Description
Hallam Nuclear Power Facility
Author: Hallam Nuclear Power Facility
Author: FIRST SODIUM REACTOR EXPERIMENT (SRE) TEST OF HALLAM NUCLEAR POWER FACILITY (HNPF) CONTROL MATERIALS.
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
An experiment was conducted in the SRE to measure temperatures and neutron flux levels in and near a boron-containing simulated control rod. The data are being used to check analytical methods developed for prediction of control rod heat generation rates and maximum temperatures in this type of control rod in the Hallam Nuclear Power Facility. The maximum observed temperatures with a reactor power level of 20 Mw were 1363 deg F for a boron-- nickel alloy ring having a 0.105-in. radial clearance with the thimble and 1100 deg F for a boron -nickel alloy ring having a 0.020-in. radial clearance. The maximum temperature difference between the coolant and the control rod was 473 deg F. It is concluded that the expected greater heat generation rates in the Hallam reactor would prohibit the use of boron-containing absorber materials in a combined a him-safety rod. (auth).
Nuclear Science Abstracts
Author: Development, Growth, and State of the Atomic Energy Industry
Author: United States. Congress. Joint Committee on Atomic EnergyPublisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 687
Book Description
Power Reactor Technology
Author: Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 1084
Book Description