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SCORE-EVET: a computer code for the multidimensional transient thermal-hydraulic analysis of nuclear fuel rod arrays. [BWR; PWR]

Description: The SCORE-EVET code was developed to study multidimensional transient fluid flow in nuclear reactor fuel rod arrays. The conservation equations used were derived by volume averaging the transient compressible three-dimensional local continuum equations in Cartesian coordinates. No assumptions associated with subchannel flow have been incorporated into the derivation of the conservation equations. In addition to the three-dimensional fluid flow equations, the SCORE-EVET code ocntains: (a) a one-… more
Date: February 1, 1978
Creator: Benedetti, R. L.; Lords, L. V. & Kiser, D. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Quarterly Progress Report on Fission Product Behavior in LWRs for the Period October-December 1977

Description: Analysis of release data obtained during High Burnup Fuel Test 10 (HBU-10) has been completed. In this test the fuel rod segment was ruptured by internal pressurization at 900/sup 0/C, at which time the temperature was rapidly increased to 1200/sup 0/C and maintained at this temperature for 10 min. Approximately 0.061% of the total cesium inventory in the rod segment was released; this was accompanied by the release of about 1.69% of the total /sup 85/Kr inventory. Moreover, about 0.022% of the… more
Date: February 1, 1978
Creator: Malinauskas, A. P.; Lorenz, R. A.; Collins, J. L.; Osborne, M. F.; Whatley, S. K. & Towns, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Argonne Code Center: benchmark problem book

Description: This report is a supplement to the original report, published in 1968, as revised. The Benchmark Problem Book is intended to serve as a source book of solutions to mathematically well-defined problems for which either analytical or very accurate approximate solutions are known. This supplement contains problems in eight new areas: two-dimensional (R-z) reactor model; multidimensional (Hex-z) HTGR model; PWR thermal hydraulics--flow between two channels with different heat fluxes; multidimension… more
Date: June 1, 1977
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Effects of a hypothetical loss-of-coolant accident on a Mark I Boiling Water Reactor pressure-suppression system

Description: A loss-of-coolant accident (LOCA) in a boiling-water-reactor (BWR) power plant has never occurred. However, because this type of accident could be particularly severe, it is used as a principal theoretical basis for design. A series of consistent, versatile, and accurate air-water tests that simulate LOCA conditions has been completed on a /sup 1///sub 5/-scale Mark I BWR pressure-suppression system. Results from these tests are used to quantify the vertical-loading function and to study the as… more
Date: December 22, 1977
Creator: Pitts, J.H. & McCauley, E.W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Finite-difference methods in multi-dimensional two-phase flow. [BWR; PWR; LMFBR]

Description: In the summer of 1974, the Theoretical Division of the Los Alamos Scientific Laboratory began several research programs in the area of reactor safety for the United States Nuclear Regulatory Commission. Research efforts were started in the Liquid Metal Fast Breeder (LMFBR) and the Light Water Reactor (LWR) safety programs. The character of the Theoretical Division was to develop computer codes for the safety analysis of these reactor systems. The question of whether or not, during the course of… more
Date: January 1, 1977
Creator: Travis, J. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Non-equilibrium aspects of water reactor safety

Description: A critical review of the thermal non-equilibrium phase change models applicable to the water reactor safety calculations is presented. Four specific areas are discussed: (1) rapid depressurization (flashing), (2) post-dryout heat transfer, (3) direct contact condensation, and (4) sub-cooled boiling. The models have been judged from a mechanistic viewpoint, and the areas where further work is needed have been pointed out. It is suggested that when a phase change occurs due to a difference in the… more
Date: July 1, 1977
Creator: Jones, O.C. Jr. & Saha, P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Data processing for the 1/5-scale Boiling Water Reactor Mark I pressure suppression experiment

Description: A description is given of methods used for data reduction and post-processing of reduced data for the 1/5-scale Boiling Water Reactor (BWR) Mark I pressure suppression experiment. Output from approximately 200 transducers, recorded onto analog magnetic tape, were reduced to engineering quantities with an analog-to-digital, COBOL-like conversion code. The reduced data were analyzed with conversational FORTRAN codes and mass-processed for reports with batch-processing FORTRAN codes.
Date: January 13, 1978
Creator: Lai, W. & McCauley, E.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Advanced converter reactors

Description: Advanced converter reactors (ACRs) of primary US interest are those which can be commercialized within about 20 years, and are: Advanced Light-Water Reactors, Spectral-Shift-Control Reactors, Heavy-Water Reactors (CANDU type), and High-Temperature Gas-Cooled Reactors. These reactors can operate on uranium, thorium, or uranium-thorium fuel cycles, but have the greatest fuel utilization on thorium type cycles. The water reactors tend to operate more economically on uranium cycles, while the HTGR … more
Date: January 1, 1979
Creator: Kasten, P. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Evaluation of improved light water reactor core designs. Final progress report, September 1979. LWRCD-20

Description: The work conducted under this research project has developed information which supports in all respects the U.S. position evolved under the NASAP/INFCE programs with respect to the near and intermediate term potential for ore conservation in LWRs on the once-through fuel cycle. Moreover, in the even longer term, it has been confirmed that contention by Edlund and others that tight-pitch Pu/UO/sub 2/ PWR cores can achieve conversion ratios which may allow these reactors to provide a competitive … more
Date: October 31, 1979
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Results from the 1/5-scale Mark I BWR pressure suppression experiment

Description: A series of consistent, versatile, and accurate air-water tests simulating LOCA conditions has been completed on the /sup 1///sub 5/-scale Mark I BWR Pressure Suppression Experimental Facility. Detailed histories of vertical loads on the wetwell are obtained in a carefully scaled three-dimensional system. In particular, variation of hydrodynamic-generated vertical loads with changes in drywell pressurization rate, downcomer submergence, and the vent-line loss coefficient were established. An in… more
Date: October 14, 1977
Creator: Pitts, J.H. & McCauley, E.W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Reports distributed under the NRC Light-Water Reactor Safety Research Foreign Technical Exchange Program. Volume III, January--June 1977

Description: Lists of documents exchanged during the first half of 1977 under agreements between the U.S. Nuclear Regulatory Commission's Office of Nuclear Regulatory Research and the governments of France, Federal Republic of Germany, and Japan are presented. During this period, the NRC received 41 reports from France, 29 from F. R. Germany, and 24 from Japan, and in return sent 107 U.S. reports to each of these three countries.
Date: September 19, 1977
Creator: Sharp, D. S. & Cottrell, W. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

WRAP: user convenient relap code package. [BWR; PWR]

Description: A modular computational system known as the Water Reactor Analysis Package (WRAP) is being developed at the Savannah River Laboratory for analysis of loss of coolant accidents (LOCA's) and other transients in water reactor systems. At this time, WRAP is essentially a reprogrammed version of the RELAP4 computer code with an extensively restructured input format, a dynamic dimensioning capability and additional computational capabilities such as an automatic steady-state option for pressurized wa… more
Date: January 1, 1977
Creator: Anderson, M.M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Status of the Fire Protection Research (FPR) Program. [BWR; PWR]

Description: The objective of the Fire Protection Research (FPR) Program under the sponsorship of the Office of Water Reactor Safety Research, USNRC, is to confirm the capability of safety features in use or planned for use in nuclear power plants. This objective is to be achieved by full scale testing and experimental and analytical evaluation of fire phenomenology.
Date: January 1, 1979
Creator: Klamerus, L.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

US NRC/LLL liaison with the Federal Republic of Germany for the GKSS-PSS steam condensation tests. Progress report No. 2

Description: This second progress report for the USNRC/LLL liaison program with the Federal Republic of Germany regarding boiling water reactor containment multivent steam condensation tests being conducted by GKSS addresses program activity during the period of July-August, 1979. During this period, the first digital data, video tapes, and complete report for test VM1 were received, together with various computer software used by GKSS for data reduction. Document handling procedures were finalized in order… more
Date: September 13, 1979
Creator: Holman, G.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

LWR-PV Surveillance Dosimetry Improvement Program review graphics

Description: A primary objective of the multilaboratory program is to prepare an updated and improved set of dosimetry, damage correlation, and the associated reactor analysis ASTM standards for LWR-PV irradiation surveillance programs. Supporting this objective are a series of analytical and experimental validation and calibration studies in Benchmark Neutron Fields, reactor Test Regions, and operating power reactor Surveillance Positions. These studies will establish and certify the precision and accuracy… more
Date: October 1, 1979
Creator: McElroy, W.N.; Gold, R. & Gutherie, G.L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

PELE-IC test problems. [BWR]

Description: This report provides prospective users of the Lawrence Livermore Laboratory (LLL) fluid-structure interaction computer code, PELE-IC, a variety of test problems for verifying the code on CDC 7600 computer systems at facilities external to the LLL environment. The test problems have been successfully run on CDC 7600 computers at the LLL and Lawrence Berkeley Laboratory (LBL) computer centers.
Date: October 1, 1979
Creator: Gong, E.Y.; Alexander, E.E.; McMaster, W.H. & Quinones, D.F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

ENFORM II: a calculational system for light water reactor logistics and effluent analysis

Description: ENFORM is a computer-based information system that addresses the material logistics, environmental releases and economics of light water reactor (LWR) operation. The most important system inputs consist of electric energy generation requirements, details of plant construction scheduling, unit costs, and environmental release factors. From these inputs the ENFORM system computes the mass balances and generates the environmental release information for noxious chemicals and radionuclides from var… more
Date: September 1, 1979
Creator: Heeb, C. M.; Lewallen, M. A.; Purcell, W. L. & Cole, B. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Effects of torus wall flexibility on forces in the Mark I Boiling Water Reactor Pressure Suppression System. Part I

Description: The authors investigated the effects of torus wall flexibility in the pressure suppression system of a Mark I boiling water reactor (BWR) when the torus wall is subjected to hydrodynamic loadings. Using hypothetical models, they examined these flexibility effects under two hydrodynamic loading conditions: (1) a steam relief valve (SRV) discharge pulse, and (2) a loss-of-coolant accident (LOCA) chugging pulse. In the analyses of these events they used a recently developed two-dimensional finite … more
Date: September 1, 1977
Creator: Martin, R. W. & McCauley, E. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Comparison of the capital costs of light water reactor and liquid metal fast breeder reactor power plants

Description: Recent studies by Atomics International, General Electric, and Westinghouse yielded capital cost estimates for a fifth of a kind LMFBR. After adjusting these estimates for plant size and converting them to 1978 dollars, they ranged from $1043 to $1495 per kWe, excluding interest during construction (IDC). These cost estimates were compared in this study with a LWR estimated by GE to cost $900 per kWe, also excluding IDC. Projecting these costs far into the future entails great uncertainty. The … more
Date: February 1, 1979
Creator: Mooz, W.E. & Siegel, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Influence of gas generation on high-temperature melt/concrete interactions. [BWR; PWR; LMFBR]

Description: Accidents involving fuel melting and eventual contact between the high temperature melt and structural concrete may be hypothesized for both light water thermal reactors and liquid metal cooled breeder reactors. Though these hypothesized accidents have a quite low probability of occurring, it is necessary to investigate the probable natures of the accidents if an adequate assessment of the risks associated with the use of nuclear reactors is to be made. A brief description is given of a program… more
Date: January 1, 1979
Creator: Powers, D.A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

LLL field test systems division support to the U. S. Nuclear Regulatory Commission. FY 1978 progress report

Description: The Lawrence Livermore Laboratory (LLL) performed technical evaluations for the U.S. Nuclear Regulatory Commission, Division of Operating Reactors, as part of a continuing program. This report summarizes the work done in FY 78 and provides references to detailed reports. Evaluations were performed on Selected Electrical, Instrumentation, and Control System Issues in existing reactors. The Select Issues investigated include reactor coolant system overpressurization protection, flooding of plant … more
Date: April 1, 1979
Creator: Rumble, R. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Complete BWR--EM LOCA analysis using the WRAP--EM system

Description: The Water Reactor Analysis Package, Evaluation Model (WRAP--EM), provides a complete analysis of postulated loss-of-coolant accidents (LOCA's) in light--water nuclear power reactors. The system is being developed at the Savannah River Laboratory (SRL) for use by the Nuclear Regulatory Commission (NRC) to interpret and evaluate reactor vendor, evaluation model (EM) analyses. The initial version of the WRAP--EM system for analysis of boiling water reactors (BWR's) is operational. To demonstrate t… more
Date: January 1, 1979
Creator: Beckmeyer, R. R.; Gregory, M. V. & Buckner, M. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Potential for fuel melting and cladding thermal failure during a PCM event in LWRs

Description: The primary concern in nuclear reactor safety is to ensure that no conceivable accident, whether initiated by a failure of the reactor system or by incorrect operation, will lead to a dangerous release of radiation to the environment. A number of hypothesized off-normal power or cooling conditions, generally termed as power-cooling-mismatch (PCM) accidents, are considered in the safety analysis of light water reactors (LWRs). During a PCM accident, film boiling may occur at the cladding surface… more
Date: January 1, 1979
Creator: El-Genk, M.S. & Croucher, D.W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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