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Critical Path Scheduling in Maintenance

Description: Summary: The following narrative interspersed with figures and attached reference exhibits is designed to acquaint the reader with the scheduling procedure developed at ORGDP, trial results and evaluation, subsequent improvement, further application, and use in conjunction with our IBM 7090 Computer.
Date: April 10, 1961
Creator: Gritzner, C. L.; Jones, J. P. & Ellis, J. M.
Partner: UNT Libraries Government Documents Department

Aircraft Reactor Test Removal and Disassembly

Description: Report documenting the dissection of a reactor called the Aircraft Reactor Test (ART). Includes the removal of the reactor from its test cell, component removal, and plans for a for a disassembly building facility.
Date: 1960?
Creator: Abbatiello, A. A. & McQuilkin, F. R.
Partner: UNT Libraries Government Documents Department

Acceptance test report for the safety class shutdown system

Description: This document provides the Acceptance Test Report for the successful testing of the Safety Shutdown Circuit. The test was done in accordance with the requirements that were defined in WHC-SD-WM-SCH-003, Interim Stabilization Safety Class Trip Circuit CGI Dedication Criteria. The actual test procedure document was contained in WHC-SD-WM-ATP-185, Acceptance Test Procedure for the Safety Class Shutdown System.
Date: October 17, 1996
Creator: Zuroff, W.F.
Partner: UNT Libraries Government Documents Department

Recirculating Beam Breakup Study for the 12 GeV Upgrade at Jefferson Lab

Description: Two new high gradient C100 cryomodules with a total of 16 new cavities were installed at the end of the CEBAF south linac during the 2011 summer shutdown as part of the 12-GeV upgrade project at Jefferson Lab. We surveyed the higher order modes (HOMs) of these cavities in the Jefferson Lab cryomodule test facility and CEBAF tunnel. We then studied recirculating beam breakup (BBU) in November 2011 to evaluate CEBAF low energy performance, measure transport optics, and evaluate BBU thresholds due to these HOMs. This paper discusses the experiment setup, cavity measurements, machine setup, optics measurements, and lower bounds on BBU thresholds by new cryomodules.
Date: July 1, 2012
Creator: Ilkyoung Shin, Todd Satogata, Shahid Ahmed, Slawomir Bogacz, Mircea Stirbet, Haipeng Wang, Yan Wang, Byung Yunn, Ryan Bodenstein
Partner: UNT Libraries Government Documents Department

The FNAL Injector Upgrade Status

Description: The new FNAL H{sup -} injector upgrade is currently being tested before installation in the Spring 2012 shutdown of the accelerator complex. This line consists of an H{sup -} source, low energy beam transport (LEBT), 200 MHz RFQ and medium energy beam transport (MEBT). Beam measurements have been performed to validate the design before installation. The results of the beam measurements are presented in this paper.
Date: May 14, 2012
Creator: Tan, C.Y.; Bollinger, D.S.; Duel, K.L.; Karns, P.R.; Lackey, J.R.; Pellico, W.A et al.
Partner: UNT Libraries Government Documents Department

Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

Description: This report fulfills the M2 milestone M2FT-13PN0912022, “Stranded Sites De-Inventorying Report.” In January 2013, the U.S. Department of Energy (DOE) issued the Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste (DOE 2013). Among the elements contained in this strategy is an initial focus on accepting used nuclear fuel from shutdown reactor sites. This focus is consistent with the recommendations of the Blue Ribbon Commission on America’s Nuclear Future, which identified removal of stranded used nuclear fuel at shutdown sites as a priority so that these sites may be completely decommissioned and put to other beneficial uses (BRC 2012). Shutdown sites are defined as those commercial nuclear power reactor sites where the nuclear power reactors have been shut down and the site has been decommissioned or is undergoing decommissioning. In this report, a preliminary evaluation of removing used nuclear fuel from 12 shutdown sites was conducted. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, and San Onofre. These sites have no other operating nuclear power reactors at their sites and have also notified the U.S. Nuclear Regulatory Commission that their reactors have permanently ceased power operations and that nuclear fuel has been permanently removed from their reactor vessels. Shutdown reactors at sites having other operating reactors are not included in this evaluation.
Date: September 30, 2013
Creator: Maheras, Steven J.; Best, Ralph E.; Ross, Steven B.; Buxton, Kenneth A.; England, Jeffery L. & McConnell, Paul E.
Partner: UNT Libraries Government Documents Department

SHUT-DOWN COOLING OF ORR

Description: Information is presented that may be used in estimating the magnitude of the shutdown cooling problem in the ORR at various power levels. The information used in the investigation was obtained from other research reactors. (W.L.H.)
Date: August 14, 1959
Creator: Cole, T.E.
Partner: UNT Libraries Government Documents Department

PERIODIC RADIATION SURVEY. CORE I, SEED 1. Section 3. Test Results T- 612394

Description: Radiation levels inside the concrete enclosures but outside the reactor plant containers after shutdown were determined. Radiation levels in the 1AC, 1BC boiler chamber enclosures and in the reactor chamber enclosure were on the average higher than in previous tests. The highest reading obtained was 7.5 mr/ hr and the lowest reading was 0.03 mr/hr; the mean level was 3.76 mr/hr as compared to 1.37 mr/hr in previous tests. (W.L.H.)
Date: June 17, 1960
Partner: UNT Libraries Government Documents Department

Advanced reactors transition FY 1997 multi-year work plan WBS 7.3

Description: This document describes in detail the work to be accomplised in FY 1997 and the out-years for the Advanced Reactors Transition (WBS 7.3) under the management of the Babcock & Wilcox Hanford Company. This document also includes specific milestones and funding profiles. Based upon the Fiscal Year 1997 Multi-Year Work Plan, the Department of Energy will provide authorization to perform the work described.
Date: September 27, 1996
Creator: Hulvey, R.K.
Partner: UNT Libraries Government Documents Department

309 Facility deactivation and decommisioning Criteria Completion Check Lists

Description: To facilitate and track completion of the 309 Facility turnover criteria completion an Applicability Matrix and Criteria Completion Check Lists were prepared. The applicability matrix documents the required turnover criteria for a given area in the facility or scope of work. The applicable criteria is selected for 16 different areas. For each area a completion checklist is provided to document completion of a requirement by WHC and the Environmental Restoration Contractor.
Date: February 1, 1996
Creator: Cornwell, B.C.
Partner: UNT Libraries Government Documents Department

Final deactivation project report on the Source Development Laboratory, building 3029, Oak Ridge National Laboratory, Oak Ridge, Tennessee

Description: The purpose of this report is to document the condition of Building 3029 after completion of deactivation activities as outlined by the DOE Nuclear Materials and Facility Stabilization Program (EM-60) guidance documentation. This report outlines the activities conducted to place the facility in a safe and environmentally sound condition for transfer to the DOE Office of Environmental Restoration (EM-40). This report provides a history and profile of the facility prior to commencing deactivation activities and a profile of the building after completion of deactivation activities. Turnover items, such as the post-deactivation surveillance and maintenance (S&M) plan, remaining hazardous materials, radiological controls, safeguards and security, quality assurance, facility operations, and supporting documentation provided in the EM-60 turnover package are discussed. Building 3029 will require access to facilitate required S&M activities to maintain the building safety envelope. building 3029 was stabilized during deactivation so that when transferred to the EM-40 program, only a minimal S&M effort would be required to maintain the building safety envelope. Other than the minimal S&M activities, the building will be unoccupied and the exterior doors locked to prevent unauthorized access. The building will be entered only to perform the required S&M. 5 refs., 7 figs., 3 tabs.
Date: May 1, 1997
Partner: UNT Libraries Government Documents Department

Effect of Temperature and Reactivity Changes in Operation of the Los Alamos Plutonium Reactor

Description: The operation of the Fast Reactor is considered in terms of normal equilibrium conditions and normal shut-down. The proposed loading, control rod adjustment and subsequent "floating" operation are discussed. Safety devices and interlocks are described. Temperature and reactivity changes are examined with respect to various system failures, phase changes, and "flashing" of the reactor. Slow changes due to faulty slug cooling are also considered. The calculations were initially based upon 10 kw operation. Performance tests of the mercury system now indicate that 20-kw operation may be feasible.
Date: May 28, 1948
Creator: Hall, David B. & Hall, Jane H.
Partner: UNT Libraries Government Documents Department

Development of Standardized Probabilistic Risk Assessment Models for Shutdown Operations Integrated in SPAR Level 1 Model

Description: Nuclear plant operating experience and several studies show that the risk from shutdown operation during Modes 4, 5, and 6 at pressurized water reactors and Modes 4 and 5 at boiling water reactors can be significant. This paper describes using the U.S. Nuclear Regulatory Commission’s full-power Standardized Plant Analysis Risk (SPAR) model as the starting point for development of risk evaluation models for commercial nuclear power plants. The shutdown models are integrated with their respective internal event at-power SPAR model. This is accomplished by combining the modified system fault trees from the SPAR full-power model with shutdown event tree logic. Preliminary human reliability analysis results indicate that risk is dominated by the operator’s ability to correctly diagnose events and initiate systems.
Date: May 1, 2008
Creator: Khericha, S. T. & Mitman, J.
Partner: UNT Libraries Government Documents Department

International Collaboration with the Shutdown of the BN-350 Reactor

Description: Representatives from the United States and the United Kingdom discussed areas where collaboration on the shutdown of the BN-350 Reactor in Aktau, Kazakhstan would benefit not only Kazakhstan, but would also help to assure the successful shutdown of the reactor. A fundamental understanding of the basis for collaboration has been for each side to ‘add value’ to each of the project areas, rather than simply substitute for each other’s experience. This approach has brought distinct technical and management benefits to the decommissioning activities in Kazakhstan.
Date: August 1, 2005
Creator: Michelbacher, J. A.; Wells, P. B.; Organ, N. & Wells, D.
Partner: UNT Libraries Government Documents Department

DETERMINATION OF THE QUANTITY OF I-135 RELEASED FROM THE AGR-1 TEST FUELS AT THE END OF ATR OPERATING CYCLE 138B

Description: The AGR-1 experiment is a multiple fueled-capsule irradiation experiment being conducted in the Advanced Test Reactor (ATR) in support of the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. The experiment began irradiation in the ATR with a cycle that reached full power on December 26, 2006 and ended with shutdown of the reactor for a brief outage on February 10, 2007 at 0900. The AGR-1 experiment will continue cyclical irradiation for about 2.5 years. In order to allow estimation of the amount of radioiodine released during the first cycle, purge gas flow to all capsules continued for about 4 days after reactor shutdown. The FPMS data acquired during part of that shutdown flow period has been analyzed to elucidate the level of 135I released during the operating cycle.
Date: May 1, 2007
Creator: Hartwell, J. K.; Scates, D. M.; Walter, J. B. & Drigert, M. W.
Partner: UNT Libraries Government Documents Department

Characteristics and fabrication of a 499 MHz superconducting deflecting cavity for the Jefferson Lab 12 geV Upgrade

Description: A 499 MHz parallel bar superconducting deflecting cavity has been designed and optimized for a possible implementation at the Jefferson Lab. Previously the mechanical analysis, mainly stress, was performed. Since then pressure sensitivity was studied further and the cavity parts were fabricated. The prototype cavity is not completed due to the renovation at Jefferson Lab which resulted in the temporary shutdown of the electron beam welding facility. This paper will present the analysis results and facts encountered during fabrication. The unique geometry of the cavity and its required mechanical strength present interesting manufacturing challenges.
Date: July 1, 2012
Creator: HyeKyoung Park, S.U. De Silva, J.R. Delayen
Partner: UNT Libraries Government Documents Department

CONCEPTUAL DESIGN OF A COUPLED BREEDING SUPERHEATING REACTOR, CBSR

Description: The conceptual design of the Coupled Breeding Superheating Reactor, CBSR, for achieving a positive breeding gain and for producing 65 Mw of electric power is presented. The design combines a steam-cooled fast region and a nonboiling pressurized light-water-cooled thermal region. The advantage offered by this arrangement as compared with that using a solid moderator in the thermal zone is that, if a power excursion occurs, the water will increase the void content and tend to limit the excursion. The total reactor power is 216 Mwt, of which 163 Mwt is used to superheat steam as it passes through the fast regions of the reactor and 53 Mwt is transferred to the pressurized water. For this power split the fast core is 4% subcritical without the reactivity contribution of the thermal region. A breeding ratio of 1.4 is calculated for an oxide-fueled fast and thermal core and a high-density, metal-fueled radial blanket. The steam throttle conditions produced are 75 atm and 453 deg C for an average fast-core power density of 500 Mw/l. The original goal of 565 deg C throttle steam temperature and 1 Mw/l power density was compromised because of the surface temperature limitation of currently available cladding materials. The system does not require a large external power source for producing the steam introduced into the fast core. This is possible through the use of a steam compressor that increases the pressure of a portion of the superheated steam and thus permits its use to generate the required saturated-steam flow rate by vaporizing the feedwater from the steam cycle. The design includes a pressure-balance system that equalizes the static pressure in both the pressurized-water and steam systems. The pressure-balance system provides a means of cooling the steam regions in an emergency by allowing the pressurized water to flash. These ...
Date: March 1, 1961
Creator: Avery, R.; Dewey, W.V.; Rohde, R. & Toppel, B.J.
Partner: UNT Libraries Government Documents Department

Re-entry Flight Demonstration Number One (RFD-1): Preflight Disassembly Analysis and Observed Disassembly of the Simulated SNAP-10A Reactor

Description: Abstract: This report describes the SNAP-10A Simulated Test Reactor, the test philosophy of Re-entry Flight Demonstration Number One, the analytical analysis of reactor disassembly, and the results of the flight test.
Date: September 1964
Creator: Klett, R. D.; Hysinger, T. M. & Robertson, M. M.
Partner: UNT Libraries Government Documents Department

Effects of Booster Scraping in Polarized Proton Runs 2006 and 2008

Description: Effects of the Booster vertical scraping on the RHIC beam polarization, the RHIC beam emittance, and on the Booster to AGS transfer efficiency and AGS transmission as well, are further studied. In [1], the strong dependence of the RHIC beam polarization and emittance on bunch intensity in proton run 2008 (pp08) is compared with the proton run 2006 (pp06), where the dependence is much weaker. The setting in the AGS Booster, mainly the vertical scraping, is suspected to having played a role in the different patterns in the two runs. In this note, we further study the effects of the Booster vertical scraping on the RHIC beam polarization, and on the RHIC beam emittance as well. With the improvement of the RHIC bunch intensity in mind, the Booster scraping effects on the Booster to AGS transfer (BtA) efficiency and the AGS transmission are also studied. For simplicity and to be more useful, only the RHIC fills after the one-week shutdown in pp06 and the fills using the AGS User 2 in pp08 are shown. For these fills, the machine settings in AGS are similar in pp06 and pp08 runs. Furthermore, this setting might be used for next polarized proton run, at least at the beginning of the run.
Date: January 2, 2009
Creator: Zhang,S.Y.; Ahrens, L.; Huang, H. & Zeno, K.
Partner: UNT Libraries Government Documents Department