WorldCat Identities

United States Office of Nuclear Energy, Science, and Technology

Overview
Works: 1,843 works in 1,921 publications in 1 language and 8,079 library holdings
Genres: Periodicals 
Roles: Sponsor, Researcher
Classifications: TK9202, 621.4830973
Publication Timeline
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Most widely held works by United States
Annual report by Nuclear Energy Research Initiative (U.S.)( )

in English and held by 236 WorldCat member libraries worldwide

Annual report by International Nuclear Energy Research Initiative (U.S.)( )

in English and held by 210 WorldCat member libraries worldwide

University currents( )

in English and held by 168 WorldCat member libraries worldwide

Nuclear reactors built, being built, or planned in the United States as of( )

in English and held by 115 WorldCat member libraries worldwide

Draft environmental impact statement for the proposed consolidation of nuclear operations related to production of radioisotope power systems by United States( Book )

1 edition published in 2005 in English and held by 11 WorldCat member libraries worldwide

Annual report by International Nuclear Energy Research Initiative (U.S.)( )

in English and held by 9 WorldCat member libraries worldwide

EBR-2 (Experimental Breeder Reactor-2) containment seismic analysis( )

2 editions published between 1989 and 1990 in English and held by 0 WorldCat member libraries worldwide

EBR-II has operated for 25 years in support of several major programs. During this time period, several of the original, non-replaceable, flow sensors, RDT sensors and thermocouples have failed in the primary system. This has led to the development of new sensors and the use of calculated values using computer models of the plant. It is important for the next generation of LMR reactors to minimize or eliminate the use of non-replaceable sensors. EBR-II is perhaps the best modeled reactor in the world, thanks to a dedicated T-H analysis program. The success of this program relied on excellent measurements of temperature and flow in subassemblies in the core. The instrumented subassemblies of the XX series provided that measurement capability. From this test series, EBR-II calculations showed that the core could withstand a loss-of-flow without scram accident and a loss-of-heat sink without scram accident from full reactor power without core damage. From this, reactor designers can now design with confidence, inherently safe reactors. 11 refs., 8 figs
Consequences of pipe ruptures in metal fueled, liquid metal cooled reactors( )

2 editions published in 1990 in English and held by 0 WorldCat member libraries worldwide

The capability to simulate pipe ruptures has recently been added to the SASSYS-1 LMR systems analysis code. Using this capability, the consequences of severe pipe ruptures in both loop-type and pool-type reactors using metal fuel were investigated. With metal fuel, if the control rods scram then either type of reactor can easily survive a complete double-ended break of a single pipe; although, as might be expected, the consequences are less severe for a pool-type reactor. A pool-type reactor can even survive a protected simultaneous breaking of all of its inlet pipes without boiling of the coolant or melting of the fuel or cladding. 2 refs., 16 figs., 1 tab
Power Burst Facility( )

4 editions published in 1990 in English and held by 0 WorldCat member libraries worldwide

This report discusses the monthly progress of the Power Burst Facility/Boron Neutron Capture Therapy (PBF/BNLT) program for cancer treatment. Highlights of the PBF/BNCT Program during July 1990 include progress within the areas of: Gross boron analysis in tissue, blood, and urine; noninvasive boron quantitative determination; analytical radiation transport and interaction modeling for BNCT; large animal model studies; neutron source and facility preparation; administration and common support and PBF operations
CFD Analysis of Core Bypass Phenomena( )

2 editions published between 2009 and 2010 in English and held by 0 WorldCat member libraries worldwide

The U.S. Department of Energy is exploring the potential for the VHTR which will be either of a prismatic or a pebble-bed type. One important design consideration for the reactor core of a prismatic VHTR is coolant bypass flow which occurs in the interstitial regions between fuel blocks. Such gaps are an inherent presence in the reactor core because of tolerances in manufacturing the blocks and the inexact nature of their installation. Furthermore, the geometry of the graphite blocks changes over the lifetime of the reactor because of thermal expansion and irradiation damage. The existence of the gaps induces a flow bias in the fuel blocks and results in unexpected increase of maximum fuel temperature. Traditionally, simplified methods such as flow network calculations employing experimental correlations are used to estimate flow and temperature distributions in the core design. However, the distribution of temperature in the fuel pins and graphite blocks as well as coolant outlet temperatures are strongly coupled with the local heat generation rate within fuel blocks which is not uniformly distributed in the core. Hence, it is crucial to establish mechanistic based methods which can be applied to the reactor core thermal hydraulic design and safety analysis. Computational Fluid Dynamics (CFD) codes, which have a capability of local physics based simulation, are widely used in various industrial fields. This study investigates core bypass flow phenomena with the assistance of commercial CFD codes and establishes a baseline for evaluation methods. A one-twelfth sector of the hexagonal block surface is modeled and extruded down to whole core length of 10.704m. The computational domain is divided vertically with an upper reflector, a fuel section and a lower reflector. Each side of the one-twelfth grid can be set as a symmetry boundary
PEBBLES Operation and Theory Manual( )

2 editions published between 2010 and 2011 in English and held by 0 WorldCat member libraries worldwide

The PEBBLES manual describes the PEBBLES code. The PEBBLES code is a computer program designed to simulation the motion, packing and vibration of spheres that undergo various mechanical forces including gravitation, Hooke's law force and various friction forces. The frictional forces include true static friction that allows non-zero angles of repose. Each pebble is individually simulated using the distinct element method
Martin Marietta Energy Systems, Inc. comprehensive earthquake management plan : Local Emergency Squads training manual( )

2 editions published in 1990 in English and held by 0 WorldCat member libraries worldwide

The training objectives are to: Describe the responsibilities of the Plant Emergency Squad during the damage assessment/abatement process and relate its importance to the protection and recovery of plant personnel following an earthquake
Evaluation of the start-up core physics tests at Japan's high temperature engineering test reactor (fully-loaded core)( )

2 editions published between 2009 and 2010 in English and held by 0 WorldCat member libraries worldwide

Advanced Fuel Cycle Cost Basis( )

3 editions published between 2007 and 2009 in English and held by 0 WorldCat member libraries worldwide

This report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models. This report contains reference cost data for 25 cost modules--23 fuel cycle cost modules and 2 reactor modules. The cost modules were developed in the areas of natural uranium mining and milling, conversion, enrichment, depleted uranium disposition, fuel fabrication, interim spent fuel storage, reprocessing, waste conditioning, spent nuclear fuel (SNF) packaging, long-term monitored retrievable storage, near surface disposal of low-level waste (LLW), geologic repository and other disposal concepts, and transportation processes for nuclear fuel, LLW, SNF, transuranic, and high-level waste
Results of the radiological survey at 7 Hancock Street, Lodi, New Jersey (LJ027)( )

2 editions published in 1989 in English and held by 0 WorldCat member libraries worldwide

Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. AT the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally ²³²Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 7 Hancock Street, Lodi, New Jersey (LJ027), was conducted during 1985 and 1986. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 5 refs., 5 figs., 3 tabs
Quantitative studies of severe fuel damage using delayed neutron data( )

7 editions published in 1990 in English and held by 0 WorldCat member libraries worldwide

Simple methods are described for bounding the passive response of a metal fueled liquid-metal cooled reactor to the chilled inlet accident. Calculation of these bounds for a prototype of the Integral Fast Reactor concept shows that failure limits -- eutectic melting, sodium boiling and fuel pin failure -- are not exceeded. 2 refs., 1 fig., 2 tabs
Results of the radiological survey at 4 Hancock Street, Lodi, New Jersey (LJ060)( )

24 editions published in 1989 in English and held by 0 WorldCat member libraries worldwide

Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally ²³²Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 4 Hancock Street, Lodi, New Jersey (LJ060), was conducted during 1985 and 1986. Gamma logging results found during this survey and during a previous survey conducted by Bechtel National, Incorporated, strongly indicated radionuclide concentrations in subsurface soil in excess of DOE remedial action criteria. This finding, coupled with the fact that adjacent properties have been found to be contaminated and that Lodi Brook apparently flows under the property, suggests that it be considered for inclusion in the DOE remedial action program. 5 refs., 4 figs., 4 tabs
Remote-Handled Low-Level Waste Disposal Project Alternatives Analysis( )

3 editions published between 2009 and 2011 in English and held by 0 WorldCat member libraries worldwide

This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy's mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site
 
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Alternative Names

controlled identityUnited States. Department of Energy

United States. Department of Energy. Office of Nuclear Energy, Science, and Technology

Languages
English (77)