[en] This document presents the results of an engineering evaluation/cost analysis (EE/CA) that was conducted to evaluate alternatives for addressing final disposition of contaminated buildings and structures in the 100-N Area of the Hanford Site. The Hanford Site is located in southeastern Washington State and is owned by the U.S. Government and operated by the U.S. Department of Energy, Richland Operations Office (RL). In November 1989, the 100 Area of the Hanford Site (as well as the 200, 300, and 1100 Areas) was placed on the U.S. Environmental Protection Agency's National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980. The 100 Area NPL includes the 100-N Area, which is in various stages of the remediation process. It has been determined by RL that hazardous substances in the 100-N Area ancillary facilities may present a potential threat to human health or the environment, and that a non-time critical removal action at these facilities is warranted. To help determine the most appropriate action, RL, in cooperation with the Washington State Department of Ecology (Ecology) and the EPA, has prepared this EE/CA. The scope of the evaluation includes the inactive contaminated ancillary facilities in the 100-N Area, the facilities residing in the buffer zone, and the Hanford Generating Plant (HGP) and the solid waste management units (SWMUs) inside HGP support facilities. The 105-N Reactor and 109-N Heat Exchange facilities are excluded from this EE/CA evaluation

[en] This Proposed Plan identifies the preferred alternatives for interim remedial action and dangerous waste unit modified closure and corrective action of the treatment, storage, and disposal (TSD) units and their associated sites in the 100-NR-1 Operable Unit, located at the Hanford Site (Figure S-1). The TSD units consist of contaminated soils, structures, and pipelines. There are four Resource Conservation and Recovery Act of 1976 (RCRA) TSD units: the 116-N-1 Crib and Trench, the 116-N-3 Crib and Trench, the 120-N-1 Percolation Pond, and the 120-N-2 Surface Impoundment. There are two associated sites: the UPR-100-N-31 unplanned release (UPR) spill site and the 100-N-58 South Settling Pond. This Proposed Plan also summarizes the other remedial alternatives analyzed for remedial action. The intent of the remedial action is to address contaminated areas that pose potential threats to human health and the environment

[en] This Proposed Plan summary includes brief descriptions of the key issues for the 100-N Area contaminated soil and groundwater. This summary is intended as a simplified introduction to readers who might not be familiar with the contaminated site cleanup process or Hanford Site issues. The detailed Proposed Plan is attached to this summary. Some of the buildings and surrounding soils in the 100 Area of the Hanford Site were contaminated during operation of the nuclear reactors. The contamination poses a potential threat to public health and/or the environment. The potential threat to the public is exposure to people on or near the site to radiation and chemicals. The potential threat to the environment is contamination in the soil that has migrated to the groundwater and could eventually harm the Columbia River. Because of these potential threats, the Federal Government decided that the 100 Area was a high priority for cleanup and placed it on the National Priorities List

No abstract available

[en] Linear elastic fracture mechanics has been used to perform a fatigue evaluation of a Canadian Deuterium Uranium (CANDU) reactor end fitting. An initial hypothetical flaw shape was assumed at a critical part of the end fitting. The effect of residual stress on the fatigue crack growth was accounted for through a growth rate model which had both range of stress intensity and maximum stress intensity as its parameters. The analysis showed that the fatigue crack growth during the estimated life of a reactor is so small that it is nearly negligible

[en] As recommended by the ICRP, the European Union (EU) agreed to abide by mandatory monitoring of radiation doses to crew during civil aviation flights operated by the airlines of the EU member states. A large number of measured and theoretically predicted values for the in-flights radiation doses of northern hemisphere flight routes are available. On the other hand very few data have been published for the southern hemisphere. This paper will present the results of Australian domestic and international return flight routes originating from Sydney. The paper also presents results of trans-hemisphere air traffic routes. Neutron and gamma doses were measured using superheated bubble dosemeters and semiconductor detectors respectively. Based on our measurements a method is suggested whereby aircrew may share their personal radiation burden by flight crew hemisphere exchange. (author)

[en] A batch of LiF thermoluminescence dosemeters (TLDs), each containing five TLD-600 and TLD-700 thermoluminescence dosemeter chips, was irradiated with 59.85 MeV per nucleon ⁸⁶Kr²⁰⁺ ions from the K1200 superconducting cyclotron at the National Superconducting Cyclotron Laboratory, Michigan State University, USA. The average linear energy transfer of the accelerated ⁸⁶Kr ions and the resulting dose imparted to the TLD chips were calculated to be 3343 keV.μm^-1 per ion and 1.68 Gy respectively. A similar batch of TLD chips was irradiated with 1.3 MeV gamma rays from a ⁶⁰Co source to 1.0 Gy. The TLD chips were evaluated at a ramp heating rate of 10 deg. C.s^-1 to 400 deg. C using a hot-finger type TLD reader. The thermoluminescence efficiency of the TLD-600 and TLD-700 dosemeters, relative to ⁶⁰Co gamma rays was calculated to be 0.0025 and 0.0027 respectively. (author)

[en] Linear elastic fracture mechanics has been used to perform a fatigue evaluation of a CANDU reactor end fitting. An initial hypothetical flaw shape was assumed at a critical part of the end fitting. The effect of residual stress on the fatigue crack growth was accounted for through a growth-rate model which had both range of stress intensity and maximum stress intensity as its parameters. The analysis showed that the fatigue crack growth during the estimated life of a reactor is negligible. (author)

[en] Microscopic dose distribution due to alpha emitting particles deposited on the inner wall of tracheobronchial tree was estimated. sup(239)Pu02 and sup(128)U308 particles were considered as alpha emitters; a computer program was used to generate the particle sizes at random and to calculate the alpha energy and LET distribution in the absorbing tissue. The dose rate, average LET and the energy distribution were given. (author)

[en] During the routine isotope production runs at the CYCLONE 30 Medical Cyclotron operated by the Australian Nuclear Science and Technology Organisation (ANSTO) a thick copper substrate electroplated with specific target material (enriched isotope) is bombarded with a 30 MeV proton beam up to 350 μA and thereby resulting in the production of intense prompt evaporation neutrons in the vicinity of the target irradiation station. A novel irradiation rig has been developed to harness these stray neutrons and used in interesting scientific applications such as, thermal neutron activation analysis of archaeological artefacts including metallic and ceramic specimens, investigation of the neutron induced radiation damage in solid state electronic devices and testing of the integrity and remaining life of superconducting materials exposed to intense neutron environment. (author)