Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 140
Book Description
Power Burst Facility, Nuclear Reactor Test Station
Power Burst Facility
Author: James G. Smith
Publisher:
ISBN:
Category : Indexes
Languages : en
Pages : 18
Book Description
Publisher:
ISBN:
Category : Indexes
Languages : en
Pages : 18
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 The reactor's four transition rods (TRs) and control rods (CRs) were present but TR boron was completely withdrawn below the core and CR boron was partially withdrawn above the core.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.
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.
Nuclear Reactors Built, Being Built, Or Planned in the United States as of ...
Power-burst Facility (PBF) Conceptual Design
Author: A. A. Wasserman
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 172
Book Description
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 172
Book Description
Power Burst Facility (PBF) Severe Fuel Damage Test 1-4
Author: David A. Petti
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 518
Book Description
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 518
Book Description
Results of the First Nuclear Blowdown Test on Single Fuel Rods (LOC-11 Series in PBF).
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
This paper presents results of the first nuclear blowdown tests (LOC-11A, LOC-11B, LOC-11C) ever conducted. The Loss-of-Coolant Accident (LOCA) Test Series is being conducted in the Power Burst Facility (PBF) reactor at the Idaho National Engineering Laboratory, near Idaho Falls, Idaho, for the Nuclear Regulatory Commission. The objective of the LOC-11 tests was to obtain data on the behavior of pressurized and unpressurized rods when exposed to a blowdown similar to that expected in a pressurized water reactor (PWR) during a hypothesized double-ended cold-leg break. The data are being used for the development and verification of analytical models that are used to predict coolant and fuel rod pressure during a LOCA in a PWR.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
This paper presents results of the first nuclear blowdown tests (LOC-11A, LOC-11B, LOC-11C) ever conducted. The Loss-of-Coolant Accident (LOCA) Test Series is being conducted in the Power Burst Facility (PBF) reactor at the Idaho National Engineering Laboratory, near Idaho Falls, Idaho, for the Nuclear Regulatory Commission. The objective of the LOC-11 tests was to obtain data on the behavior of pressurized and unpressurized rods when exposed to a blowdown similar to that expected in a pressurized water reactor (PWR) during a hypothesized double-ended cold-leg break. The data are being used for the development and verification of analytical models that are used to predict coolant and fuel rod pressure during a LOCA in a PWR.
Reactor Safeguards
Author: Charles R. Russell
Publisher: Elsevier
ISBN: 1483138860
Category : Science
Languages : en
Pages : 405
Book Description
Reactor Safeguards focuses on the measures and approaches in the safeguard of reactors. The book first discusses the development of nuclear reactors, including the emergence of radiation hazards, construction of nuclear reactors in Chicago, and containment of reactors. The text also focuses on radioactive materials; reactor kinetics; and control and safety systems of reactors. The text discusses the containment of nuclear reactors. Topics include nuclear excursions; combustion of reactor materials; melting of reactor fuels; design of containment structures; and size of breaks or leaks in cooling systems. The text also describes the dispersion of radioactive materials, including problems in operations, diffusion theory, and nomograms for graphical solutions. The book also highlights the possible damages that a nuclear reactor accident can produce. Considerations include the permissible dose of radiation, exposure to nuclear radiations, and evacuation from a contaminated area. The text is a valuable source of data for readers, engineers, and physicists who are responsible in hazard analysis and site selection.
Publisher: Elsevier
ISBN: 1483138860
Category : Science
Languages : en
Pages : 405
Book Description
Reactor Safeguards focuses on the measures and approaches in the safeguard of reactors. The book first discusses the development of nuclear reactors, including the emergence of radiation hazards, construction of nuclear reactors in Chicago, and containment of reactors. The text also focuses on radioactive materials; reactor kinetics; and control and safety systems of reactors. The text discusses the containment of nuclear reactors. Topics include nuclear excursions; combustion of reactor materials; melting of reactor fuels; design of containment structures; and size of breaks or leaks in cooling systems. The text also describes the dispersion of radioactive materials, including problems in operations, diffusion theory, and nomograms for graphical solutions. The book also highlights the possible damages that a nuclear reactor accident can produce. Considerations include the permissible dose of radiation, exposure to nuclear radiations, and evacuation from a contaminated area. The text is a valuable source of data for readers, engineers, and physicists who are responsible in hazard analysis and site selection.
AEC Authorizing Legislation, Fiscal Year 1968: Reactor development program, March 14 and 15, 1967
Author: United States. Congress. Joint Committee on Atomic Energy
Publisher:
ISBN:
Category :
Languages : en
Pages : 908
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 908
Book Description
Department of Energy Compliance with the National Environmental Policy Act
Author: United States. Congress. House. Committee on Merchant Marine and Fisheries. Subcommittee on Fisheries and Wildlife Conservation and the Environment
Publisher:
ISBN:
Category : Energy conservation
Languages : en
Pages : 100
Book Description
Publisher:
ISBN:
Category : Energy conservation
Languages : en
Pages : 100
Book Description