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Title: Physics of reactor safety. Quarterly report, April--June 1977. [LMFBR]

Abstract

The work in the Applied Physics Division includes reports on reactor safety program by members of the Reactor Safety Appraisals Group, Monte Carlo analysis of safety-related critical assembly experiments by members of the Theoretical Fast Reactor Physics Group, and planning of safety-related critical experiments by members of the Zero Power Reactor (ZPR) Planning and Experiments Group. Work on Reactor core thermal-hydraulic code development performed in the Components Technology Division is also included in the report.

Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
OSTI Identifier:
7286844
Report Number(s):
ANL-77-69
DOE Contract Number:
W-31-109-ENG-38
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; LMFBR TYPE REACTORS; REACTOR SAFETY; RESEARCH PROGRAMS; CLINCH RIVER BREEDER REACTOR; CONTROL ROD WORTHS; FLUID FLOW; HEAT TRANSFER; LOSS OF FLOW; MATHEMATICAL MODELS; PRIMARY COOLANT CIRCUITS; REACTIVITY COEFFICIENTS; REACTIVITY INSERTIONS; REACTIVITY WORTHS; REACTOR ACCIDENTS; VOID COEFFICIENT; ACCIDENTS; BREEDER REACTORS; COOLING SYSTEMS; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; POWER REACTORS; REACTIVITY; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; SODIUM COOLED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210500 - Power Reactors, Breeding

Citation Formats

None. Physics of reactor safety. Quarterly report, April--June 1977. [LMFBR]. United States: N. p., 1977. Web. doi:10.2172/7286844.
None. Physics of reactor safety. Quarterly report, April--June 1977. [LMFBR]. United States. doi:10.2172/7286844.
None. Thu . "Physics of reactor safety. Quarterly report, April--June 1977. [LMFBR]". United States. doi:10.2172/7286844. https://www.osti.gov/servlets/purl/7286844.
@article{osti_7286844,
title = {Physics of reactor safety. Quarterly report, April--June 1977. [LMFBR]},
author = {None},
abstractNote = {The work in the Applied Physics Division includes reports on reactor safety program by members of the Reactor Safety Appraisals Group, Monte Carlo analysis of safety-related critical assembly experiments by members of the Theoretical Fast Reactor Physics Group, and planning of safety-related critical experiments by members of the Zero Power Reactor (ZPR) Planning and Experiments Group. Work on Reactor core thermal-hydraulic code development performed in the Components Technology Division is also included in the report.},
doi = {10.2172/7286844},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Sep 01 00:00:00 EDT 1977},
month = {Thu Sep 01 00:00:00 EDT 1977}
}

Technical Report:

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  • Technical efforts were concentrated on improving the HAARM-2 code primarily by adding the results of the sodium oxide agglomerate measurements, on formulating the mathematical basis for reference code development, on investigating the possibilities for using polynomials to express particle size distributions in the reference code, and on evaluating the use of a laser Doppler interferometry system to measure sodium oxide agglomerate sizes. Details of efforts performed and progress made on tasks in these several general areas are discussed.
  • Information is presented concerning accident energetics; core debris behavior; sodium containment and structural integrity; research for elevated temperature design criteria; fuel motion detection; ACPR fuel motion system; and advanced reactor safety research assessment.
  • Reactor safety studies involving HTGR, LWR, LMFBR, and GCFR type reactors are summarized.
  • This version of SAS4A/LEVITATE is now operating successfully for the most part and is being applied to analysis of the TREAT L6 and L7 experiments. Application of the RAS version of SAS4A/LEVITATE to an EOC-4 LOF case for the CRBR showed substantial axial fuel dispersal to occur within 100 ms after pin failure, with the dispersal becoming very large by 250 ms. Both fission gas and sodium vapor effects appeared to be important in this dispersal. Considerable improvements have been made in the development version of SAS4A/PLUTO2/LEVITATE relating to the way fission gas is handled. The BIFLO code for analysismore » of two-dimensional sodium boiling in a fuel assembly is being modified to implement a more implicit numerical formulation, an equation of state for pure vapor, and lateral heat conduction between sodium flow channels. In the area of single-phase code development work (COMMIX-1A; COMMIX-1B) the implementation of three turbulence models and two different schemes have been completed. In the area of two-phase works, COMMIX-2 computer code, the efforts are continued in developing both models, the two-fluid model and the homogeneous equilibrium model with slip.« less
  • This Quarterly progress report summarizes work done during the months of April-June 1979 in Argonne National Laboratory's Applied Physics and Components Technology Divisions for the Division of Reactor Safety Research of the US Nuclear Regulatory Commission. The work in the Applied Physics Division includes reports on reactor-safety research and technical coordination of the RSR safety analysis program by members of the Reactor Safety Appraisals Group, Monte Carlo analysis of safety-related critical assembly experiments by members of the Reactor Computations Group, and planning of safety-related critical experiments by members of the Zero Power Reactor (ZPR) Planning and Experiments Group. Work onmore » reactor core thermal-hydraulics was performed in ANL's Components Technology Division.« less