Shield-verification survey of a large hot cell at the FFTF

Prevo, P. R.

Title: Shield-verification survey of a large hot cell at the FFTF

Full Record
Other Related Research

Abstract

This paper describes a radiation shield verification survey of a large hot cell at the Fast Flux Test Facility (FFTF). The following aspects of the shield test are discussed: description of the FFTF; description of the hot cell; the test procedures; radiation protection, and the test results.

Authors:: Prevo, P. R.

Publication Date:: Tue Jan 01 00:00:00 EST 1980

Research Org.:: Hanford Engineering Development Lab., Richland, WA (USA)

OSTI Identifier:: 6373252

Report Number(s):: HEDL-SA-2044; CONF-800735-3
TRN: 81-010444

DOE Contract Number:: AC14-76FF02170

Resource Type:: Conference

Resource Relation:: Conference: Healthy Physics Society summer school, Seattle, WA, USA, 14 Jul 1980

Country of Publication:: United States

Language:: English

Subject:: 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; FFTF REACTOR; HOT CELLS; SHIELDING; PERFORMANCE TESTING; SPECIFICATIONS; EPITHERMAL REACTORS; EQUIPMENT; FAST REACTORS; LABORATORY EQUIPMENT; LIQUID METAL COOLED REACTORS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SODIUM COOLED REACTORS; TEST REACTORS; TESTING; 220600* - Nuclear Reactor Technology- Research, Test & Experimental Reactors

Citation Formats


                    Prevo, P. R. Shield-verification survey of a large hot cell at the FFTF.  United States: N. p., 1980. 
        Web.

Copy to clipboard


                    Prevo, P. R. Shield-verification survey of a large hot cell at the FFTF.  United States.

Copy to clipboard


                    Prevo, P. R. 1980.  
        "Shield-verification survey of a large hot cell at the FFTF".  United States.  https://www.osti.gov/servlets/purl/6373252.

Copy to clipboard


                    
@article{osti_6373252,

  title        = {Shield-verification survey of a large hot cell at the FFTF},

  author       = {Prevo, P. R.},

  abstractNote = {This paper describes a radiation shield verification survey of a large hot cell at the Fast Flux Test Facility (FFTF). The following aspects of the shield test are discussed: description of the FFTF; description of the hot cell; the test procedures; radiation protection, and the test results.},

  doi          = {},

  url          = {https://www.osti.gov/biblio/6373252},
  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {Tue Jan 01 00:00:00 EST 1980},

  month        = {Tue Jan 01 00:00:00 EST 1980}

}

Copy to clipboard

Conference:

View Conference (0.24 MB)

Other availability

Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that hold this conference proceeding.

Save / Share:

Export Metadata

Save to My Library

Similar records in OSTI.GOV collections:

FFTF shield and gamma-ray measurements

Conference Bunch, W; Moore, F; Stinson, W

An extensive measurements program was carried out prior to routine operation of the Fast Flux Test Facility (FFTF) to establish (1) the attenuation characteristics of the reactor shield, (2) the nuclear environment in the core, and (3) to assure that the facility could be operated safely from the standpoint of radiological considerations. Reactor shield neutron fluxes were measured primarily using radioactivant detectors irradiated in special test vehicles placed at assessible locations. Preliminary evaluation of the data indicated shield performance consistent with design calculations. Gamma ray measurements employed a variety of ionization chambers and calorimeters as well as thermoluminescent dosimeters, selfpoweredmore »« less
Material open test assembly processing at the FFTF's IEM cell. [Interim examination and maintenance]

Conference Danko, A

The Interim Examination and Maintenance (IEM) Cell is a vertical hot cell located within the containment dome of the Fast Flux Test Facility (FFTF). The cell has two basic functions: (1) to perform disassembly/reassembly and nondestructive testing on radioactive, sodium-wetted reactor components, and (2) to provide a shielded work volume where radioactive, sodium-wetted reactor and refueling equipment can be repaired and maintained. One of the recent FFTF experiments processed through the IEM Cell was the Material Open Test Assembly (MOTA). This paper describes the disassembly and reassembly of the MOTA test assembly.
FFTF operating experience with sodium natural circulation: slides included

Conference Burke, T; Additon, S; Beaver, T; ...

The Fast Flux Test Facility (FFTF) has been designed for passive, back-up, safety grade decay heat removal utilizing natural circulation of the sodium coolant. This paper discusses the process by which operator preparation for this emergency operating mode has been assured, in paralled with the design verification during the FFTF startup and acceptance testing program. Over the course of the test program, additional insights were gained through the testing program, through on-going plant analyses and through general safety evaluations performed throughout the nuclear industry. These insights led to development of improved operator training material for control of decay heat removalmore »« less
Full Text Available
FFTF shield and gamma ray measurements

Conference Bunch, W; Carter, L; Moore, Jr, F; ...

Shield measurements and four cycles of operating experience have shown the design and construction of radiation shields for the Fast Flux Test Facility (FFTF) reactor and plant to be satisfactory. A number of minor shield deficiencies were found and corrected. Most of these were associated with interfaces between components, each of which was satisfactory by itself. Preliminary evaluation of the shield measurements indicates satisfactory agreement with design calculations. Operator doses to date have been quite small, especially when compared to light water reactor experience.
Analysis of in-core coolant temperatures of FFTF instrumented fuels tests at full power

Conference Hoth, C

Two full size highly instrumented fuel assemblies were inserted into the core of the Fast Flux Test Facility in December of 1979. The major objectives of these instrumented tests are to provide verification of the FFTF core conditions and to characterize temperature patterns within FFTF driver fuel assemblies. A review is presented of the results obtained during the power ascents and during irradiation at a constant reactor power of 400 MWt. The results obtained from these instrumented tests verify the conservative nature of the design methods used to establish core conditions in FFTF. The success of these tests also demonstratesmore »« less
Full Text Available

Similar Records