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Summary of HTGR (high-temperature gas-cooled reactor) benchmark data from the high temperature lattice test reactor

Description: The High Temperature Lattice Test Reactor (HTLTR) was a unique critical facility specifically built and operated to measure variations in neutronic characteristics of high temperature gas cooled reactor (HTGR) lattices at temperatures up to 1000{degree}C. The Los Alamos National Laboratory commissioned Pacific Northwest Laboratory (PNL) to prepare this summary reference report on the HTLTR benchmark data and its associated documentation. In the initial stages of the program, the principle of th… more
Date: October 1, 1989
Creator: Newman, D.F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Potential minimum cost of electricity of superconducting coil tokamak power reactors

Description: The potential minimum cost of electricity (COE) for superconducting tokamak power reactors is estimated by increasing the physics (confinement, beta limit, bootstrap current fraction) and technology (neutral beam energy, toroidal field (TF) coil allowable stresses, divertor heat flux, superconducting coil critical field, critical temperature, and quench temperature rise) constraints far beyond those assumed for ITER until the point of diminishing returns is reached. A version of the TETRA syste… more
Date: January 1, 1989
Creator: Reid, R.L. & Peng, Y-K. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Large break loss-of-coolant accident analyses for the high flux isotope reactor

Description: The US Department of Energy's High Flux Isotope Reactor (HFIR) was analyzed to evaluate it's response to a spectrum of loss-of-coolant accidents (LOCAs) with potential for leading to core damage. The MELCOR severe accident analysis code (version 1.7.1) was used to evaluate the overall dynamic response of HFIR. Before conducting LOCA analyses, the steady-state thermal-hydraulic parameters evaluated by MELCOR for various loop sections were verified against steady-state operating data. Thereafter,… more
Date: January 1, 1989
Creator: Taleyarkhan, R.P. (Oak Ridge National Lab., TN (USA))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Multiloop integral system test (MIST): Final report, Inter-group comparisons

Description: The multiloop integral system test (MIST) was part of a multiphase program started in 1983 to address small-break loss-of-coolant accidents (SBLOCAs) specific to Babcock and Wilcox-designed plants. MIST was sponsored by the US Nuclear Regulatory Commission, the Babcock and Wilcox Owners Group, the Electric Power Research Institute, and Babcock and Wilcox. The unique features of the Babcock and Wilcox design, specifically the hot leg U-bends and steam generators, prevented the use of existing in… more
Date: July 1, 1989
Creator: Gloudemans, J.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Additional capabilities and benchmarking with the SPERT transients for heavy water application of the PARET code

Description: The capabilities of the PARET code have been expanded to include the ability to compute steady-state and transient results for heavy water reactors. A comparison is provided between PARET and the SPERT II series of transients. Another significant improvement in the code is the addition of a restart capability. The current capabilities of the code are summarized. 7 refs., 12 figs., 3 tabs.
Date: January 1, 1989
Creator: Woodruff, W.L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Safety research programs sponsored by Office of Nuclear Regulatory Research: Progress report, January 1--March 31, 1989

Description: This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Division of Systems Research of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research following the reorganization in July 1988. The previous reports have covered the period October 1, 1976 through December 31, 1988.
Date: August 1, 1989
Creator: Weiss, A. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactivity measurements on an experimental assembly of 4. 31 wt % sup 235 U enriched UO sub 2 fuel rods arranged in a shipping cask geometry

Description: A research program was initiated for the US Department of Energy (DOE) Sandia National Laboratory Transportation Systems Development Department in 1982 to provide benchmark type experimental criticality data in support of the design and safe operations of nuclear fuel transportation systems. The overall objective of the program is to identify and provide the experimental data needed to form a consistent, firm, and complete data base for verifying calculational models used in the criticality ana… more
Date: October 1, 1989
Creator: Bierman, S.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Portable parallel programming in a Fortran environment

Description: Experience using the Argonne-developed PARMACs macro package to implement a portable parallel programming environment is described. Fortran programs with intrinsic parallelism of coarse and medium granularity are easily converted to parallel programs which are portable among a number of commercially available parallel processors in the class of shared-memory bus-based and local-memory network based MIMD processors. The parallelism is implemented using standard UNIX (tm) tools and a small number… more
Date: January 1, 1989
Creator: May, E.N.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Vectorization of Monte Carlo particle transport

Description: Fully vectorized versions of the Los Alamos National Laboratory benchmark code Gamteb, a Monte Carlo photon transport algorithm, were developed for the Cyber 205/ETA-10 and Cray X-MP/Y-MP architectures. Single-processor performance measurements of the vector and scalar implementations were modeled in a modified Amdahl's Law that accounts for additional data motion in the vector code. The performance and implementation strategy of the vector codes are related to architectural features of each ma… more
Date: January 1, 1989
Creator: Burns, P. J.; Christon, M.; Schweitzer, R.; Lubeck, O. M.; Wasserman, H. J.; Simmons, M. L. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

A new simulation method for the efficient calculation of benchmarks for detonation products equations of state

Description: A new variation on the Monte Carlo method is presented here in the context of its potential impact on the development of detonation products equations of state (EOS). The configurational density of states and other quantities are determined for a nonstandard reference simulation. Then the EOS for a linear combinations of potentials is evaluated through a density of states transformation at arbitrary densities and temperatures in the fluid range. The computer time required for the EOS calculatio… more
Date: January 1, 1989
Creator: Shaw, M.S. (Los Alamos National Lab., NM (USA))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Verification and validation plan for reactor analysis computer codes

Description: This report presents a verification and validation (V&V) plan for reactor analysis computer codes used in Technical Specifications development and for other safety and production support calculations. This plan fulfills the commitments by Westinghouse Savannah River Company (WSRC) to the Department of Energy Savannah River (DOE-SR) as identified in a letter to R.E. Tiller (Reference 1). The plan stresses verification and validation by demonstrating successful application of the codes to predict… more
Date: November 1, 1989
Creator: Toffer, H.; Crowe, R. D.; Schwinkendorf, K. N. & Pevey, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Verification and validation plan for reactor analysis computer codes

Description: This report presents a verification and validation (V V) plan for reactor analysis computer codes used in Technical Specifications development and for other safety and production support calculations. This plan fulfills the commitments by Westinghouse Savannah River Company (WSRC) to the Department of Energy Savannah River (DOE-SR) as identified in a letter to R.E. Tiller (Reference 1). The plan stresses verification and validation by demonstrating successful application of the codes to predict… more
Date: November 1, 1989
Creator: Toffer, H.; Crowe, R.D.; Schwinkendorf, K.N. (Westinghouse Hanford Co., Richland, WA (United States)) & Pevey, R.E. (Westinghouse Savannah River Co., Aiken, SC (United States))
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Comparison of US/FRG accident condition fuel failure and release models

Description: Although there are many differences between the High-Temperature Gas Cooled Reactor (HTGR) concepts being developed in the US and the High Temperature Reactor (HTR) concepts in the Federal Republic of Germany (FRG), the coated fuel particles are very similar. Significant benefits are achievable through cooperative research and exchange of information and data on the fuel performance and radionuclide retention in the coated fuel particles. This draft report describes cooperative work on HTGR saf… more
Date: May 29, 1989
Creator: Bolin, J. & Dunn, T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

MCNP photon transport benchmarking calculations performed at SRP. Revision 1

Description: Monte Carlo methods have long been used at the Savannah River Laboratory (SRL) to perform criticality calculations for many different processes. To perform transport analyses (both neutron and photon) a two-dimensional infinite lattice integral transport code (GLASS) has been used. The neutron transport portion of the code has been benchmarked against other codes and experimental data. The photon transport portion of the code, which is used to calculate gamma redistribution in the event of a lo… more
Date: 1989-06~
Creator: White, A. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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