WorldCat Identities

Idaho National Engineering Laboratory

Overview
Works: 2,092 works in 2,530 publications in 1 language and 23,961 library holdings
Genres: Handbooks, manuals, etc  Periodicals 
Roles: Researcher, Monitor
Classifications: TK9166, 621.48380973
Publication Timeline
Key
Publications about Idaho National Engineering Laboratory Publications about Idaho National Engineering Laboratory
Publications by Idaho National Engineering Laboratory Publications by Idaho National Engineering Laboratory
Most widely held works about Idaho National Engineering Laboratory
 
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Most widely held works by Idaho National Engineering Laboratory
Nuclear computerized library for assessing reactor reliability (NUCLARR) ( Book )
in English and held by 321 WorldCat member libraries worldwide
This Reference Guide contains instructions on how to install and use Version 3.5 of the NRC-sponsored Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR). The NUCLARR data management system is contained in compressed files on the floppy diskettes that accompany this Reference Guide. NUCLARR is comprised of hardware component failure data (HCFD) and human error probability (HEP) data, both of which are available via a user-friendly, menu driven retrieval system. The data may be saved to a file in a format compatible with IRRAS 3.0 and commercially available statistical packages, or used to formulate log-plots and reports of data retrieval and aggregation findings
Classification of transportation packaging and dry spent fuel storage system components according to importance to safety by J. W McConnell ( )
2 editions published in 1996 in English and held by 266 WorldCat member libraries worldwide
Quality assurance inspections for shipping and storage containers by H. M Stromberg ( )
2 editions published in 1996 in English and held by 231 WorldCat member libraries worldwide
This is a guide for conducting quality assurance inspections of transportation packaging and dry spent fuel storage system suppliers. (Suppliers are defined as designers, fabricators, distributors, users or owners of those packaging and storage systems.) This guide may be used during inspection to determine regulatory compliance with 10 CFR, Part 71, Subpart H; 10 CFR, Part 72, Subpart G; 10 CFR, Part 21; and supplier's quality assurance program commitments. It was developed to provide a structured, consistent approach to inspections. The guidance therein provides a framework for evaluation of transportation packaging and dry spent fuel storage systems quality assurance programs. Inspectors are provided with the flexibility to adapt the methods and concepts to meet inspection requirements for the particular facility. The method used in the guide treats each activity at a facility as a separate performance element and combines the activities within the framework of an''inspection tree.''The method separates each performance element into several areas for inspection and identifies guidelines, based on regulatory requirements, to qualitatively evaluate each area. This guide also serves as a field manual to facilitate quality assurance inspection activities. This guide replaces an earlier one, NUREG/CR-5717 (Packing Supplier Inspection Guide). This replacement guide enhances the inspection activities for transportation packagings and adds the dry spent fuel storage system quality assurance inspection activities
Characteristics of low-level radioactive decontamination waste ( )
in English and held by 108 WorldCat member libraries worldwide
Examples, clarifications, and guidance on preparing requests for relief from pump and valve inservice testing requirements by C. B Ransom ( Book )
2 editions published in 1996 in English and held by 104 WorldCat member libraries worldwide
International code assessment and applications program summary of code assessment studies concerning RELAP5/MOD2, RELAP5/MOD3, and TRAC-B by Richard R Schultz ( Book )
1 edition published in 1993 in English and held by 97 WorldCat member libraries worldwide
Annual report of the TMI-2 EPICOR-II resin/liner investigation : Low-level Waste Data Base Development Program for fiscal year 1988 ( Book )
3 editions published in 1988 in English and held by 94 WorldCat member libraries worldwide
Field lysimeter investigations Low-Level Waste Data Base Development Program for fiscal year ( )
in English and held by 91 WorldCat member libraries worldwide
Systems analysis programs for hands-on integrated reliability evaluations (SAPHIRE), version 5.0 ( Book )
in English and held by 87 WorldCat member libraries worldwide
LOFT experimental measurements uncertainty analyses ( Book )
in English and held by 85 WorldCat member libraries worldwide
Microbial degradation of low-level radioactive waste ( )
in English and held by 85 WorldCat member libraries worldwide
Steam generator tube failures ( Book )
2 editions published in 1996 in English and held by 84 WorldCat member libraries worldwide
TMI-2 vessel investigation project integration report ( Book )
2 editions published in 1994 in English and held by 83 WorldCat member libraries worldwide
TRAC-BF1/MOD1 an advanced best-estimate computer program for BWR accident analysis ( Book )
2 editions published in 1992 in English and held by 83 WorldCat member libraries worldwide
Developing and assessing accident management plans for nuclear power plants ( Book )
2 editions published in 1992 in English and held by 83 WorldCat member libraries worldwide
Release of radionuclides and chelating agents from cement-solidified decontamination low-level radioactive waste collected from the Peach Bottom Atomic Power Station Unit 3 by D. W Akers ( Book )
2 editions published in 1994 in English and held by 82 WorldCat member libraries worldwide
As part of a study being performed for the Nuclear Regulatory Commission (NRC), small-scale waste-form specimens were collected during a low oxidation-state transition-metal ion (LOMI)-nitric permanganate (NP)-LOMI solidification performed in October 1989 at the Peach Bottom Atomic Power Station Unit 3. The purpose of this program was to evaluate the performance of cement-solidified decontamination waste to meet the low-level waste stability requirements defined in the NRC's ''Technical Position on Waste Form, '' Revision 1. The samples were acquired and tested because little data have been obtained on the physical stability of actual cement-solidified decontamination ion-exchange resin waste forms and on the leachability of radionuclides and chelating agents from those waste forms. The Peach Bottom waste-form specimens were subjected to compressive strength, immersion, and leach testing in accordance with the NRC's ''Technical Position on Waste Form, '' Revision 1. Results of this study indicate that the specimens withstood the compression tests (>500 psi) before and after immersion testing and leaching, and that the leachability indexes for all radionuclides, including ¹⁴C, ⁹⁹{Tc}, and ¹²⁹I, are well above the leachability index requirement of 6.0, required by the NRC's ''Technical Position on Waste Form, '' Revision 1
Motor-operated valve research update ( Book )
2 editions published in 1992 in English and held by 82 WorldCat member libraries worldwide
Light water reactor lower head failure analysis ( Book )
2 editions published in 1993 in English and held by 82 WorldCat member libraries worldwide
Implications for accident management of adding water to a degrading reactor core ( Book )
2 editions published in 1994 in English and held by 82 WorldCat member libraries worldwide
This report evaluates both the positive and negative consequences of adding water to a degraded reactor core during a severe accident. The evaluation discusses the earliest possible stage at which an accident can be terminated and how plant personnel can best respond to undesired results. Specifically discussed are (a) the potential for plant personnel to add water for a range of severe accidents, (b) the time available for plant personnel to act, (c) possible plant responses to water added during the various stages of core degradation, (d) plant instrumentation available to understand the core condition and (e) the expected response of the instrumentation during the various stages of severe accidents
 
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Audience Level
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Audience Level
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Audience level: 0.81 (from 0.01 for Geologic m ... to 0.93 for Characteri ...)
Alternative Names

controlled identity Idaho National Engineering and Environmental Laboratory

controlled identity National Reactor Testing Station, Idaho (U.S.)

controlled identity United States. Department of Energy. Idaho Operations Office

controlled identity United States. Department of Energy. Office of Energy Technology

controlled identity United States. Department of Energy. Office of Health and Environmental Research

Engineering Laboratory
Engineering Laboratory Idaho Falls, Idaho
INEL
INEL Abkuerzung
National Engineering Laboratory
National Engineering Laboratory Idaho Falls, Idaho
United States. Department of Energy. Idaho Operations Office. Idaho National Engineering Laboratory
United States. Department of Energy. Office of Energy Technology. Idaho National Engineering Laboratory
United States. Department of Energy. Office of Health and Environmental Research. Idaho National Engineering Laboratory
United States. Dept. of Energy. Idaho Operations Office. Idaho National Engineering Laboratory
United States. Dept. of Energy. Office of Energy Technology. Idaho National Engineering Laboratory
United States Idaho National Engineering Laboratory
Languages
English (92)