Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Power Burst Facility, National Reactor Testing Station, Idaho
Author: Environmental Statement
Author: National Reactor Testing Station, Idaho (U.S.)Publisher:
ISBN:
Category : Materials testing reactors
Languages : en
Pages : 121
Book Description
Power Burst Facility, Nuclear Reactor Test Station
Author: Power Burst Facility
Author: James G. SmithPublisher:
ISBN:
Category : Indexes
Languages : en
Pages : 18
Book Description
Draft Environmental Statement
Author: National Reactor Testing Station, Idaho (U.S.)Publisher:
ISBN:
Category : Materials testing reactors
Languages : en
Pages : 72
Book Description
Draft Environmental Impact Statement
Author: National Reactor Testing Station, Idaho (U.S.)Publisher:
ISBN:
Category : Materials testing reactors
Languages : en
Pages : 72
Book Description
Power Burst Facility
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The Power Burst Facility (PBF) reactor operated from 1972 to 1985 on the SPERT Area I of the Idaho National Laboratory, then known as Nuclear Reactor Test Station. PBF was designed to provide experimental data to aid in defining thresholds for and modes of failure under postulated accident conditions. PBF reactor startup testing began in 1972. This evaluation focuses on two operational loading tests, chronologically numbered 1 and 2, published in a startup-test report in 1974 [1]. Data for these tests was used by one of the authors to validate a MCNP model for criticality safety purposes [2]. Although specific references to original documents are kept in the text, all the reactor parameters and test specific data presented here was adapted from that report. The tests were performed with operational fuel loadings, a stainless steel in-pile tube (IPT) mockup, a neutron source, four pulse chambers, two fission chambers, and one ion chamber. The reactor's four transition rods (TRs) and control rods (CRs) were present but TR boron was completely withdrawn below the core and CR boron was partially withdrawn above the core. Test configurations differ primarily in the number of shim rods, and consequently the number of fuel rods included in the core. The critical condition was approached by incrementally and uniformly withdrawing CR boron from the core. Based on the analysis of the experimental data and numerical calculations, both experiments are considered acceptable as criticality safety benchmarks.
Loss of Fluid Test Facility, National Reactor Testing Station
Author: Publisher:
ISBN:
Category : LOFT (Nuclear reactor safety test facility)
Languages : en
Pages : 140
Book Description
Hearings and Reports on Atomic Energy
Author: United States. Congress. Joint Committee on Atomic EnergyPublisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1218
Book Description
Executive Impoundment of Appropriated Funds
Author: United States. Congress. Senate. Committee on the Judiciary. Subcommittee on Separation of PowersPublisher:
ISBN:
Category : Executive impoundment of appropriated funds
Languages : en
Pages : 652
Book Description