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Nuclear safety criteria for special test loads -- N-Reactor

Description: The initial fuel landing for the N-Reactor and the use of a specific alternative fuel element are described in a previous report. It is highly probable that it will also be desirable in the future to irradiate still other types of fuel elements in the reactor. If the test is of small scale, fever than five channels, or if these elements vary only slightly from the initial fuel load (or any other fuel type approved for large-scale use at some future date), the irradiation will be accomplished wi… more
Date: October 14, 1963
Creator: Nechodom, W. S. & Miller, N. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

CONTAINMENT VESSEL TEMPERATURE FOR PU-238 HEAT SOURCE CONTAINER UNDER AMBIENT, FREE CONVECTION AND LOW EMISSIVITY COOLING CONDITIONS

Description: The EP-61 primary containment vessel of the 5320 shipping package has been used for storage and transportation of Pu-238 plutonium oxide heat source material. For storage, the material in its convenience canister called EP-60 is placed in the EP-61 and sealed by two threaded caps with elastomer O-ring seals. When the package is shipped, the outer cap is seal welded to the body. While stored, the EP-61s are placed in a cooling water bath. In preparation for welding, several containers are remove… more
Date: February 14, 2011
Creator: Gupta, N. & Smith, A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

DEVELOPMENT OF THE BULK TRITIUM SHIPPING PACKAGING

Description: A new radioactive shipping packaging for transporting bulk quantities of tritium, the Bulk Tritium Shipping Package (BTSP), has been designed for the Department of Energy (DOE) as a replacement for a package designed in the early 1970s. This paper summarizes significant design features and describes how the design satisfies the regulatory safety requirements of the Code of Federal Regulations and the International Atomic Energy Agency. The BTSP design incorporates many improvements over its pre… more
Date: September 14, 2008
Creator: Blanton, P. & Eberl, K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Neutron Capture Cross Section Measurement on $^{238}$Pu at DANCE

Description: The proposed neutron capture measurement for {sup 238}Pu was carried out in Nov-Dec, 2010, using the DANCE array at LANSCE, LANL. The total beam-on-target time is about 14 days plus additional 5 days for the background measurement. The target was prepared at LLNL with the new electrplating cell capable of plating the {sup 238}Pu isotope simultaneously on both sides of the 3-{micro}m thick Ti backing foil. A total mass of 395 {micro}g with an activity of 6.8 mCi was deposited onto the area of 7 … more
Date: February 14, 2011
Creator: Chyzh, A & Wu, C Y
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

EBS Radionuclide Transport Abstraction

Description: The purpose of this report is to develop and analyze the engineered barrier system (EBS) radionuclide transport abstraction model, consistent with Level I and Level II model validation, as identified in Technical Work Plan for: Near-Field Environment and Transport: Engineered Barrier System: Radionuclide Transport Abstraction Model Report Integration (BSC 2005 [DIRS 173617]). The EBS radionuclide transport abstraction (or EBS RT Abstraction) is the conceptual model used in the total system perf… more
Date: July 14, 2006
Creator: Prouty, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SEEPAGE/INVERT INTERACTIONS

Description: As directed by a written development plan (CRWMS M&O 1999a), a conceptual model for water entering the drift and reacting with the invert materials is to be developed. The purpose of this conceptual model is to assist Performance Assessment Operations (PAO) and its Engineered Barrier Performance Department in modeling the geochemical environment within a repository drift, thus allowing PAO to provide a more detailed and complete in-drift geochemical model abstraction, and to answer the key … more
Date: April 14, 2000
Creator: Domski, P.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

105-KE Isolation Barrier Leak Rate Acceptance Test Report

Description: This Acceptance Test Report (ATR) contains the completed and signed Acceptance Procedure (ATP) for the 105-KE Isolations Barrier Leak Rate Test. The Test Engineer`s log, the completed sections of the ATP in the Appendix for Repeat Testing (Appendix K), the approved WHC J-7s (Appendix H), the data logger files (Appendices T and U), and the post test calibration checks (Appendix V) are included.
Date: June 14, 1995
Creator: McCracken, K. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Vent clearing during a simulated loss-of-coolant accident in Mark I boiling-water-reactor pressure-suppression system

Description: The response of the pressure-suspension containment system of Mark I boiling-water reactors to a loss-of-coolant accident (LOCA) is being studied. This response is a design basis for light-water nuclear reactors. Part of the study is being carried out on a /sup 1///sub 5/-scale experimental facility that models the pressure-suppression containment system of the Peach Bottom 2 nuclear power plant. The test series reported here focused on the initial or air-clearing phase of a hypothetical LOCA. … more
Date: February 14, 1978
Creator: Pitts, J.H. & McCauley, E.W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Review of Hanford production reactor confinement (Project CGI-791)

Description: The Project CGI-791, Reactor Confinement for Hanford production reactors, vas conceived as a result of deliberations concerning the release of the Wahluke Slope secondary exclusion zone for private use, and initiated by an authorization and directive from the Atomic Energy Commission to proceed with such a project on a high priority basis. This authorization was coupled with the establishment of limits on reactor heat-generation rates and fission product inventories. These limits were to be re-… more
Date: October 14, 1960
Creator: Trumble, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

MATERIALS COMPATIBILITY OF SNAP FUEL COMPONENTS DURING SHIPMENT IN 9975 PACKAGING

Description: Materials Science and Technology has evaluated materials compatibility for the SNAP (Systems for Nuclear Auxiliary Power) fuel for containment within a 9975 packaging assembly for a shipping period of one year. The evaluation included consideration for potential for water within the convenience can, corrosion from water, galvanic corrosion, tape degradation, and thermal expansion risk. Based on a review of existing literature and assumed conditions, corrosion and/or degradation of the 304 stain… more
Date: November 14, 2006
Creator: Vormelker, P
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Overview of the Safety Issues Associated with the Compressed Natural Gas Fuel System and Electric Drive System in a Heavy Hybrid Electric Vehicle

Description: This report evaluates the hazards that are unique to a compressed-natural-gas (CNG)-fueled heavy hybrid electric vehicle (HEV) design compared with a conventional heavy vehicle. The unique design features of the heavy HEV are the CNG fuel system for the internal-combustion engine (ICE) and the electric drive system. This report addresses safety issues with the CNG fuel system and the electric drive system. Vehicles on U. S. highways have been propelled by ICEs for several decades. Heavy-duty ve… more
Date: November 14, 2002
Creator: Nelson, S. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Stress analysis of LOFT containment vessel attachments for the mainsteam and feedwater piping support structures

Description: The LOFT Containment Vessel attachments for the Mainsteam and Feedwater Piping Support Structures have been analyzed for operating and faulted loading conditions. This report contains the analysis of the connections to the containment vessel for the most current design and loading. Also contained in this report is the analysis of the piping supports.
Date: September 14, 1977
Creator: Finicle, D. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Effect of Radiation Damage on SM-1, SM-1A and PM-2A Reactor Vessels

Description: Report describing the status of the SM-1, SM-1A, and PM-2A reactors, specifically regarding the effects "of irradiation on nil-ductility transition temperature and the associated problem of brittle fracture." (p. iii)
Date: October 14, 1961
Creator: McLaughlin, D. W.; Rowekamp, B. J.; Chittum, R. A.; Coombe, J. R.; Kelleman, R. W.; Bobe, P. E. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Engineered Barrier System performance requirements systems study report. Revision 02

Description: This study evaluates the current design concept for the Engineered Barrier System (EBS), in concert with the current understanding of the geologic setting to assess whether enhancements to the required performance of the EBS are necessary. The performance assessment calculations are performed by coupling the EBS with the geologic setting based on the models (some of which were updated for this study) and assumptions used for the 1995 Total System Performance Assessment (TSPA). The need for enha… more
Date: January 14, 1997
Creator: Balady, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SAFETY ENGINEERING FOR THE RELATIVISTIC HEAVY ION COLLIDER AT THE BROOKHAVEN NATIONAL LABORATORY.

Description: THERE ARE ONLY A FEW OTHER HIGH ENERGY PARTICLE ACCELERATORS LIKE RHIC IN THE WORLD. THEREFORE, THE DESIGNERS OF THE MACHINE DO NOT ALWAYS HAVE CONSENSUS DESIGN STANDARDS AND REGULATORY GUIDANCE AVAILABLE TO ESTABLISH THE ENGINEERING PARAMETERS FOR SAFETY. SOME OF THE AREAS WHERE STANDARDS ARE NOT AVAILABLE RELATE TO THE CRYOGENIC SYSTEM, CONTAINMENT OF LARGE VOLUMES OF FLAMMABLE GAS IN FRAGILE VESSELS IN THE EXPERIMENTAL APPARATUS AND MITIGATION OF A DESIGN BASIS ACCIDENT WITH A STORED PARTICL… more
Date: November 14, 1999
Creator: Musolino, S. V.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Double-shell tank waste system assessment status and schedule

Description: The integrated program for completing the integrity assessments of the dangerous waste tank systems managed by the Tank Waste Remediation System (TWRS) Division of Westinghouse Hanford Company is presented in the Tank Waste Remediation System Tank System Integrity Assessments Program Plan, WHC-SD-AP017, Rev. 1. The program plan identified the assessment requirements and the general scope to which these requirements applied. Some of these assessment requirements have been met and others are eith… more
Date: June 14, 1995
Creator: Walter, E.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Lease Operations Environmental Guidance Document

Description: This report contains discussions in nine different areas as follows: (1) Good Lease Operating Practices; (2) Site Assessment and Sampling; (3) Spills/Accidents; (4) Containment and Disposal of Produced Waters; (5) Restoration of Hydrocarbon Impacted Soils; (6) Restoration of Salt Impacted Soils; (7) Pit Closures; (8) Identification, Removal and Disposal of Naturally Occurring Radioactive Materials (NORM); and (9) Site Closure and Construction Methods for Abandonment Wells/Locations. This report… more
Date: February 14, 2001
Creator: Management, Bureau of Land
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Modeling of Cation Binding in Hydrated 2:1 Clay Minerals - Final Report

Description: Hydrated 2:1 clay minerals are high surface area, layered silicates that play a unique role in determining the fate of radionuclides in the environment. This project consisted of developing and implementing computer simulation methods for molecular characterization of the swelling and ion exchange properties of Hydrated 2:1 clay minerals, and the subsequent analysis and theoretical modeling with a view toward improving contaminant transport modeling as well as soil remediation and radionuclide … more
Date: September 14, 2000
Creator: Smith, David E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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