Proceedings of the 24th DOE/NRC Nuclear Air Cleaning and ... · PDF fileKWOC INDEX ON CONFERENCE TITLES Title Revision of Reactor Accident Source Terms and Implications for Nuclear

Keyword Plant

Plant

Plant

Plant

Plant

Plant

Plant

Plant

Plant

Plant-Internal

Plants

Plants

Plants

Plants

Plants

Plants

Plate

Pleat

Plenum

Plenums

Plenums

Policies

Pollution

Polygonal

Polygonal

Pool

24th DOE/NRC NUCLEAR AIR CLEANING AND TREATMENT CONFERENCE

21-24 DOE/NRC NUCLEAR AIR CLEANING AND TREATMENT CONFERENCES KWOC INDEX ON CONFERENCE TITLES

Title

Air Cleaning Programs Relating to the First Japanese Commercial

The Development and Design of the Off-Gas Treatment System for the

An Introduction to the Design, Commissioning, and Operation of Nuclear

NAUAHYGROS - A Code for Calculating Aerosol Behavior in Nuclear

Ventilation System Design for Control of Radioactive Airborne Particulates

Heating, Ventilating, and Air Conditioning Deactivation Thermal Analysis

Basis for and Practical Methods of Controlling Painting Activities at the

Removal Efficiency of Silver Impregnated Filter Materials and

Control of Radio-Iodine at the German Reprocessing Plant Wak During

The Link Between Off-Site-Emergency Planning and Plant-internal

Notes on the Draft NUREG Report Accident Source Terms for

Application of ASME Code AG-1 to YGN 3 & 4 Plants, South Korea

Changes to Licensing for U.S. Nuclear Power Plants

Containment Venting Sliding Pressure Venting Process for PWR and

An Evaluation of Efforts by Nuclear Power Plants to Use ASTM D3803-89

Disposal of Slightly Contaminated Radioactive Wastes from Nuclear

Experimental Study on the Volatile Ruthenium Decontamination Factor of

The Effect of Media Area on the Dust Holding Capacity of Deep Pleat

Progress Report on the In-Place Acceptance Tests of Walk-In Plenum

Proposed Retrofit of HEPA Plenums with Injection and Sampling

Potential for HEPA Filter Damage from Water Spray Systems in Filter

Application of Innovative Policies for Controlling Radionuclide Releases:

Testing Cleanable/Reusable HEPA Prefilters for Mixed Waste Incinerator

Behavior of the Loaded Polygonal HEPA Filter Exposed to Water Droplets

Behavior of the Polygonal HEPA Filter Exposed to Water Droplets Carried

Experimental Study on Aerosol Removal Effect by Pool Scrubbing

983

Conference No. - Page 2 I-0984

23-0333

23-0439

23-0520

23-0784

24-0471

24-0534

24-0609

24-0618

23-0509

22-0734

22-0223

22-0341

2 l-0876

23-0078

23-0138

22-0244

24-0743

21-0360

23-0721

24-0752

24-0040

24-0076

22-0534

21-0772

22-0453

Keyword Pool

Pool

Portable

Post-Accident

Post-Accident

Potential

Potential

Potential

Potential

Power

Power

Power

Power

Power

Power

Power

Power

Power

Power

Power

Predict

Predicting

Prefilter

Prefilter/HEPA

Prefilters

Prefilters



Title

Pool Fires in a Large Scale Ventilation System

Experimental Study on Aerosol Removal Efficiency for Pool Scrubbing

Potential Radionuclide Emissions from Stacks on the Hanford Site, Part 2:

Direct Post-Accident Sampling System for Containment Atmospheres

Post-Accident Air Leakage Analysis in a Nuclear Facility via T-Method

Proposed Source Term Revisions Potential Impact on Future Nuclear Air





22-0374

22-0736

23-0269

23-0498

24-0752

22-0734

22-0018

22-0341

22-066 1

21-0057

21-0695

23-0078

23-0138

23-0439

23-0520

24-0181

24-0065

22-0554

22-0443

22-0554

24-0076

24-0788

The Nuclear Industry’s Plan to Achieve New Nuclear Power Plant Orders

Changes to Licensing for U.S. Nuclear Power Plants

Testing of Adsorbents Used in Nuclear Power Plant Air Cleaning Systems

Radiological Health Effects Models for Nuclear Power Plant Accident

Optimization of Air Ducts for Nuclear Reactor Power Generation Station

An Evaluation of Efforts by Nuclear Power Plants to Use ASTM D3803-89


An Introduction to the Design, Commissioning, and Operation of Nuclear


Testing the Sampling Efficiency of a Nuclear Power Station Stack Monitor

Development of a Computer Code to Predict a Ventilation Requirement

Predicting Mass Loading as a Function of Pressure Difference Across

Design of a Prefilter to Improve Radiation Protection and Filtering



Extended-Life Nuclear Air Cleaning Filters Via Dynamic Exclusion

984

Conference No. - Page 2 l-0844

21-0918

23-0269

22-0283


Keyword Preliminary

Preliminary

Pressure

Pressure

Pressure

Pressure

Pressure

Pressure

Pressure

Pretreatment

Probe

Produced

Products

Program-Current

Programs

Programs

Programs

Programs

Programs

Programs

Programs

Programs

Progress

Progress

Progress

Progress


Title

Preliminary Field Evaluation of High Efficiency Steel Filters

Preliminary Studies to Determine the Shelf Life of HEPA Filters


Mathematical Models for Changes in HEPA Filter Pressure Drop Caused


Effects of the Particle Penetration Inside the Filter Medium on the HEPA

Effect of Humidity on the Filter Pressure Drop

A Low Pressure Filter System for New Containment Concepts

Variable Pattern Contamination Control Under Positive Pressure

Simulation Test of Aerosol Generation from Vessels in the Pretreatment

Single Point Aerosol Sampling: Evaluation of Mixing and Probe

Aerosol Concentrations Produced by a Laskin Nozzle Generator a

Study on Collecting Efficiency of Fission Products by Spray:

DOE Waste Management Program-Current and Future

High Efficiency and Ultra Low Penetration Aerosol Filter Test Programs by

The Dutch Nuclear Programs

Nuclear Air Cleaning R&D Programs in Canada

United Kingdom Atomic Energy Authority Programs

Nuclear Air Cleaning Programs in Progress in France

A Short Overview of the Programs in Sweden


Nuclear Air Cleaning Programs in Hungary


Nuclear Air Cleaning Programs in Progress in France

Progress and Challenges in Cleaning Up Hanford

Performance Testing of HEPA Filters: Progress Towards a European

985

Conference No. - Page 23-0195

23-0613

22-0554

21-0671

2 I-0876

21-0128

23-0187

23-0478

24-0428

24-0778

23-0217

21-0109

24-0500

22-0716

22-0324

21-0968

21-0971

21-0975

21-0978

21-0980

2 I-0984

2 l-0986

21-0360

21-0978

24-0335

24-08 19

Keyword Project

Project

Projection

Protection

Protection

Protocols

Prototype

Pulse

Pulses

Purex

Purge

Purging

Qinshan

Qualification

Quality

Quickmix

R&D

Radial

Radiation

Radiation

Radioactive

Radioactive

Radioactive

Radioactive

Radioactive

Radioactive



Conference Title No. - Page

The Phebus FP Integral Source Term Experimental Project with 22-0464

The Integrated Melter Off-Gas Treatment Systems at the West Valley 23-0016

A Real-Time Stack Radioactivity Monitoring System and Dose Projection 23-0259

Design of a Prefilter to Improve Radiation Protection and Filtering 22-0443

Development of a Personal Computer Code for Fire Protection Analysis of 22-0875

Control Room Envelope Unfiltered Air Inleakage Test Protocols 24-0400

Design and Characteristics of Annulus Ventilation and HVAC System for 22-0791

Accuracy Improvement in Leak Detection of Charcoal Adsorbers by 24-0176

A New Method for In-Situ Filter Testing Using Pulses of Aerosol and 22-0154

Heating, Ventilating, and Air Conditioning Deactivation Thermal Analysis 24-0471

AP600 Containment Purge Radiological Analysis 23-0454

Kinetic Modelling of the Purging of Activated Carbon After Short Term 21-0662

An Introduction to the Design, Commissioning, and Operation of Nuclear 23-0439

Challenges of Equipment Qualification Using Today’s Standards with 23-0034

Quality Assurance Requirements for NESHAPS Compliance 21-0352

Development of the Quickmix Injector for In-Situ Filter Testing 22-0163

Nuclear Air Cleaning R&D Programs in Canada 21-0971

Radial Flow Systems for the Nuclear Industry 22-0527

Design of a Prefilter to Improve Radiation Protection and Filtering 22-0443

The Influence of Salt Aerosol on Alpha Radiation Detection by WIPP 24-0188

Measurement of Cesium Emissions During the Vitrification of Simulated 22-0253

The Experience with the Effectiveness of Filtering Systems for the 22-0393

Parametric Studies of Radioactive Iodine, Hydrogen Iodide and Methyl 22-0646

Air Cleaning Technologies for the Management and Disposal of 21-0028

Elimination of Iodine from Radioactive Gaseous Effluents in a Packed 21-0259

Photochemical Removal of Radioactive Iodine from Air 2 l-0376

986

Keyword Radioactive

Radioactive

Radioactive

Radioactive

Radioactive

Radioactive

Radioactive

Radioactive

Radioactive

Radioactive

Radioactive

Radioactivity

Radioactivity

Radioiodine

Radioiodine

Radioiodine

Radiological

Radiological

Radionuclide

Radionuclide

Radionuclide

Radionuclide

Radionuclide

Radionuclide

Reactor

Reactor



Title

The Incineration of Low Level Radioactive Wastes - Current Status

IAEA Decadal Activities in the Field of Radioactive Gaseous Waste

Impact of the Filtered Venting System Design Upon the Total Radioactive

Generation and Release of Radioactive Gases in LLW Disposal Facilities

Numerical Analysis of a Natural Convection Cooling System for


Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities


Radioactive Waste Tank Ventilation System Incorporating Tritium Control


Validation Testing of Radioactive Waste Drum Filter Vents

Activated Charcoal Beds for Passive Mitigation of the Radioactivity

A Real-Time Stack Radioactivity Monitoring System and Dose Projection

A Study of the Effect of Coatings Operation on Radioiodine Removing

Characterization and Restoration of Performance of “Aged” Radioiodine


Radiological Health Effects Models for Nuclear Power Plant Accident

AP600 Containment Purge Radiological Analysis

BARCT: A Conservative Approach to Regulating Radionuclide Emissions

Radionuclide Air Emissions at Department of Energy Facilities

EPA Perspective on Radionuclide Aerosol Sampling





GE’s Advanced Nuclear Reactor Designs

987

Conference No. - Page 2 I-0488

21-0635

2 l-0933

23-0115

23-0128

23-0138

23-0250

23-0784

24-0051

24-0065

24-0683

22-0428

23-0259

21-0563

24-0520

24-0618

2 I-0057

23-0454

22-0233

23-0233

23-0241

23-0269

23-0498

24-0040

22-0736

22-0043

Keyword Reactor

Reactor

Reactors

Reactors

Reactors

Real-Time

Real-Time

Real-Time

Real-Time

Reclamation

Reduction

Redundant

Region

Regulating

Regulation

Regulatory

Regulatory

Regulatory

Release

Release

Release

Release

Release

Releases

Reliability-Case

Removing



Title

Revision of Reactor Accident Source Terms and Implications for Nuclear


Severe Accident Issues for Advanced Reactors

Air Cleaning Requirements for Evolutionary and Advanced Reactors

Revised Accident Source Terms for Light-Water Reactors

Real-Time Detection of a Fluorescent Aerosol Application to the Efficiency

CAIRE - A Real-Time Feedback System for Emergency Response


Development of Real Time Detector for Fluorescent Particles

A Thick Homogeneous Vegetated Cover Design Proves Cost- and

Tritium Emissions Reduction Facility (TERF)


Response of NRC Region III to Perceived Lack of Filter Testing Expertise

BARCT: A Conservative Approach to Regulating Radionuclide Emissions

Bar Coded Air Sample Tracking: How It Can Assist in Compliance with

Changing Winds in NRC’s Regulatory Environment

US NRC Regulatory Guidance for Engineered Safety Feature Air

Developments in the Area of Regulatory Matters in the UK

Minimizing of Iodine-129 Release in the Karlsruhe Reprocessing Plant

Beta Experiments on Aerosol Release During Melt-Concrete Interaction



Generation and Release of Radioactive Gases in LLW Disposal Facilities


Modern Technology Tools for Improvement of NPP Reliability-Case Study

A Study of the Effect of Coatings Operation on Radioiodine Removing

988


21-0695

22-0034

21-0016

23-0488

21-0095

21-0646

23-0259

24-0163

24-0118

22-0065

21-0360

22-0762

22-0233

23-0670

21-0343

21-0626

21-0977

22-0075

22-0415

22-0428

21-0933

23-0115

24-0040

22-0808

2 l-0563

Keyword Removing

Replace

Replacement

Replacement

Replacement

Replacement

Replacement

Reprocessing

Reprocessing

Reprocessing

Reprocessing

Reprocessing

Reprocessing

Reprocessing

Reprocessing

Reprocessing

Requirements

Residence

Resistance

Resolution

Respirators

Response

Response

Responsibility

Restoration

Retention



Title


New Performance Data for “Emery 3002” and “Emery 3004,” Two

An Update: DOP Replacement in Testing Machines for Filters and

Replacement Tracer Agent for the In-Place Leak Testing of Adsorbers in

Safe Replacement Materials for DOP in “Hot Smoke” Aerosol

An Example of a Component Replacement when Applying ASME N509

Halide Test Agent Replacement Study


The Development of Corona Discharge for Iodine Removal from Nuclear

Removal of Iodine-129 from Dissolver Off-Gas of Reprocessing Plant by

Retention and Measurement of Iodine-129 and of Organoiodine in the







Residence Time Determination for Adsorbent Beds of Different

Development and Evaluation of a HEPA Filter for Increased Strength and

Value-Impact Assessment for Resolution of Generic Safety Issue 143 -

An Update: DOP Replacement in Testing Machines for Filters and

Response of NRC Region III to Perceived Lack of Filter Testing Expertise


Clean Air and Clear Responsibility



989


23-0743

22-0146

22-0698

21-0126

23-0093

23-0313

22-0075

22-o 102

22-0118

2 I-0222

2 I-0984

23-0333

24-0609

24-0618

24-0778

22-0736

23-0308

22-0617

23-0380

22-0146

22-0762

2 I-0646

23-0658

24-0520

21-0222

.,-..__ l__.-._^~.

Keyword Retention

Retention

Retention

Retrofit

Retrospective

Review

Review

Review

Review

Review

Review

Revision

Revision

Revision

Revisions

Revisions

Revisted

River

Room

Room

Room

Room

Rule

Ruthenium

Ruthenium

Ruthenium



Title

Iodine-129 Distribution and Retention During Evaporation of MWL

Factors Affecting the Retention of Methyl Iodide by Iodide-Impregnated

The Retention of Iodine in Stainless Steel Sample Lines


The First Twenty Years of the ASME Committee on Nuclear Air and Gas

Review of Department of Energy HEPA Filter Test Activities FY 1990 - FY

A Review of Gas Phase Filtration Standards and their Applicability to

A Review of the History, Revisions and Interrelationships of ANSI/ASME

Review of Department of Energy Filter Test Facility and Filter Test Facility

Review of In-Place HEPA Filter Testing at Several DOE Facilities

A Review of DOE HEPA Filter Component Test Activities: FY-1994


Section TA Acceptance Testing, Draft Revision 03106196

ASME N511-19xX, Standard for Periodic In-Service Testing of Nuclear Air


A Review of the History, Revisions and Interrelationships of ANSI/ASME

The Case for Improved HEPA-Filter Mechanical Performance Standards

ASME N510 Test Results for Savannah River Site AACS Filter

Revised Accident Source Terms and Control Room Habitability

Control Room Inleakage Testing Using Tracer Gases at Zion Generating

Design Basis Documentation for the Control Room Ventilation/Chilled

Control Room Envelope Unfiltered Air Inleakage Test Protocols



Behavior and Control of Ruthenium During Operation of the New Waste

Behavior of Ruthenium in the Case of Shutdown of the Cooling System of

990


2 l-0583

23-0279

23-0721

24-0807

22-0177

22-02 15

21-0320

21-0385

23-0766

24-0631

22-0362

24-0203

24-0264

22-0736

21-0320

24-0829

23-0068

22-0742

22-0830

21-0526

24-0400

24-0040

22-0244

2 I-0467

21-0831

Keyword s-3

Safe

Safe

Safety

Safety

Safety

Safety

Salt

Salt

Salt

Sampler

Sampling

Sampling

Sampling

Sampling

Sampling

Sampling

Sampling

Sampling

Sampling

Sand

Savannah

Scale

Scale

Scale

Scanning



Title

Field Measurement of the Performance of Air Cleaning Systems to


New Performance Data for “Emery 3002” and “Emery 3004,” Two

Heater Selection Criteria for Engineered Safety Features Atmosphere

Department of Energy Directions in Environment, Safety, and Health

US NRC Regulatory Guidance for Engineered Safety Feature Air


Structural Testing of Salt Loaded HEPA Filters for WIPP

Investigation of Salt Loaded HEPA Filters

The Influence of Salt Aerosol on Alpha Radiation Detection by WIPP

Development of Filter Systems - Part 2, Injection Systems and Multi-Point


Aerosol Particle Losses in Sampling Systems

Confirmation of Automatic Flow Control for a Gaseous Effluent Sampling


EPA Perspective on Radionuclide Aerosol Sampling

Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities

Experimental Study on the Particles Deposition in the Sampling Duct



Design and Full Scale Test of a Sand Bed Filter


Technical Scale Iodine Expulsion from the Dissolver Solution and Balance


Design and Full Scale Test of a Sand Bed Filter

Method for HEPA Filter Leak Scanning with Differentiating Aerosol


21-0126

23-0743

22-0820

21-0005

2 I-0626

23-0380

22-0262

2 I-0366

24-0188

21-0139

22-0283

22-03 10

21-0415

23-02 17

23-0241

23-0250

23-0539

23-0721

24-0181

21-0946

23-0068

2 I-0247

2 l-0844

2 I-0946

24-0671

991



Title Keyword Scattering

Schedule-Effective

Scrubber

Scrubbing

Scrubbing

Seismically

Selection

Selective

Self-Contained

Sellafield

Separation

Separation

Sequoyah

Series

Session

Severe

Severe

Severe

Severe

Shear

Shelf

Shut

Shutdown

Silos

Silver

Silver

Simulated Performances of a Single Particle Laser Light Scattering



Experimental Study on Aerosol Removal Effect by Pool Scrubbing


Aerosol Penetration Through a Seismically Loaded Shear Wall


The Phebus FP Integral Source Term Experimental Project with

Evaluation of Self-Contained HEPA Filter


Development of a Process for Adsorptive Separation of KR-85 from the

Development of Silver Impregnated Alumina for Iodine Separation from

Basis for and Practical Methods of Controlling Painting Activities at the


Panel Session: Changes to ASME Code AG-1, Section FC, HEPA Filters

Severe Accident Issues for Advanced Reactors





Preliminary Studies to Determine the Shelf Life of HEPA Filters




Removal of Iodine-129 from Dissolver Off-Gas of Reprocessing Plant by

Removal Characteristics of Some Organic Iodine Forms by Silver

992


24-0118

22-0244

22-0453

21-0918

22-0402

22-0820

22-0464

23-0054

23-0333

21-0299

23-0352

24-0534

21-0360

24-0850

22-0034

22-0428

21-0933

23-0520

22-0402

23-0613

24-0618

21-0831

23-0784

22-0118

21-0594

Keyword Silver

Silver

Silver

Silver

Simulated

Simulated

Simulated

Simulation

Simulation

Simulations

Single

Single

Single

Site

Site

Site

Site

Sites

Sites

Sliding

Slightly

Smoke

Solution

Solutions

Solutions

Solutions



Title

Development of Silver Impregnated Alumina for Iodine Separation from

Influences of Impurities on Iodine Removal Efficiency of Silver Alumina

Diffusional Analysis of the Adsorption of Methyl Iodide on Silver


Measurement of Cesium Emissions During the Vitrification of Simulated



Post-Accident Air Leakage Analysis in a Nuclear Facility via T-Method


Filtration Theory Using Computer Simulations


A Single Standard for In-Place Testing of DOE HEPA Filters






Air Cleaning Issues with Contaminated Sites






Iodine Stripping from Nitric Solutions in IATEMA

Iodine-129 Distribution and Retention During Evaporation of MWL

A Study on the Explusion of Iodine from Spent-Fuel Solutions

993


24-0563

24-0576

24-0609

22-0253

21-0173

21-0435

22-0374

24-0778

24-0485

21-0173

23-0096

23-0217

21-0435

23-0068

23-0269

23-0498

24-0012

24-0118

2 I-0876

23-0138

21-0126

2 I-0247

22-0091

2 l-0234

23-0321

Keyword Source

Source

Source

Source

Source

Source

Source

Spectroscopy

Spent

Spent-Fuel

Spokane

Sponsors

Spray

Spray

Spray

Stack

Stack

Stack

Stacks

Stacks

Stainless

Stainless

Standard

Standard

Standard

Standard



Title






A Utility Perspective on New Source Terms



Behavior of Iodine in the Dissolution of Spent Nuclear Fuels

A Study on the Explusion of Iodine from Spent-Fuel Solutions


Opening Comments of Chairman and Greetings from Sponsors

Experimental Study of Elementary Collection Efficiency of Aerosols by

Study on Collecting Efficiency of Fission Products by Spray:







Technical Brief Stainless Steel Filter for Nuclear Air Cleaning


The Difficulty of Testing Non-509 Systems to the N510 Standard

A Single Standard for In-Place Testing of DOE HEPA Filters

ASME N511-19xX, Standard for Periodic In-Service Testing of Nuclear Air

Performance Testing of HEPA Filters: Progress Towards a European

994


22-0736

22-0742

22-0362

22-0464

22-0732

23-0488

23-0269

24-0550

23-0321

24-0118

24-0002

23-0682

24-0500

24-0752

23-02 17

23-0259

24-0181

23-0269

23-0498

2 l-0424

23-0279

21-0318

23-0096

24-0264

24-0819

Keyword Standardized

Standards

Standards

Standards

Standards

Standards

Standards

Statement

Station

Station

Station

Station

Station

Station

Stations

Status

Steam

Steel

Steel

Steel

Steel

Steel

Steel

Steps

Storage

Storage



Title

Standardized Methods for In-Place Filter Testing

A Review of Gas Phase Filtration Standards and their Applicability to


European Community Nuclear Codes and Standards

Challenges of Equipment Qualification Using Today’s Standards with

Integrating Industry Nuclear Codes and Standards into United States

The Case for Improved HEPA-Filter Mechanical Performance Standards

Introductory Statement


Testing of Non-N509 Filter Systems - Audit Experiences at McGuire

Comments on Testing of Non-N509 Filter Systems -Audit Experiences at




Demonstration of Carbon-14 Removal at Candu Nuclear Generating



Development and Evaluation of a Cleanable High Efficiency Steel Filter


High Efficiency Steel Filters for Nuclear Air Cleaning

Preliminary Field Evaluation of High Efficiency Steel Filters


Further Development of the Cleanable Steel HEPA Filter and Comparison

Steps Towards the Minimization of Particulate Emissions From a



995


22-0215

22-0661

21-0212

23-0034

23-0098

24-0829

21-0186

22-0830

21-0329

21-0332

21-0526

21-0695

24-0181

21-0530

21-0488

21-0918

22-0586

2 I-0424

21-0733

23-0195

23-0279

24-0708

21-0510

21-0831

23-0128

Keyword Storage

Streams

Streams

Streams

Strength

Striking

Stripping

Structural

Substitute

support

Surveillance

Survey

Sweden

System

System

System

System

System

System

System

System

System

System

System

System

System



Title


The Application of HEPA Filter Units in Gas Streams of High Dust


Development of Silver impregnated Alumina for Iodine Separation from



Iodine Stripping from Nitric Solutions in IATEMA


Aerosol Concentrations Produced by a Laskin Nozzle Generator a


Practical Experience Applied to the Design of Injection and Sample

Survey of Life-Cycle Costs of Glass-Paper HEPA Filters

A Short Overview of the Programs in Sweden



Performance Characterization of a New CAM System


Development of Computer Design System for HVAC System

Development of Computer Design System for HVAC System

Design and Characteristics of Annulus Ventilation and HVAC System for

Concept for a Passive Heat Removal and Filtration System Under Core

New Injection System for a Short Mixing of Test Aerosols and Gas

Confirmation of Automatic Flow Control for a Gaseous Effluent Sampling




996


22-0540

2 I-0222

23-0352

22-0617

21-0247

22-0091

22-0262

21-0109

21-0385

24-O 132

22-0849

21-0980

22-0283

22-0283

22-0299

22-0443

22-078 1

22-0781

22-0791

22-0863

2 l-0080

21-0415

2 I-0526

2 I-0646

21-0831

Keyword System

System

System

System

System

System

System

System

System

System

System

System

System

System

System

Systematic

Systems

Systems

Systems

Systems

Systems

Systems

Systems

Systems

Systems

Systems



Title


Measurement System for Alpha and Beta Aerosols with Wide Dynamic

lnvestigtions into the Design of a Filter System for PWR Containment





Constant Depression Fan System: A Novel Glovebox Ventilation System


A Low Pressure Filter System for New Containment Concepts



Development of an Air Cleaning System for Dissolving High Explosives

Effects of Welding Fumes on Nuclear Air Cleaning System Carbon


A Systematic Study on the Effectiveness of Mono Alkyl lodides of Cyclic

Aerosol Particle Losses in Sampling Systems

The Experience with the Effectiveness of Filtering Systems for the

Challenges Within Ventilation Systems During Accident Situations

Radial Flow Systems for the Nuclear Industry


Application of High-Efficiency Metal Fiber Filters in Ventilation Systems of




Development of a Personal Computer Code for Fire Protection Analysis of

997


21-0872

21-0898

21-0933

23-0128

23-0259

23-0333

23-0404

23-0404

23-0478

23-0784

24-0051

24-0089

24-0525

24-0778

21-0394

22-0310

22-0393

22-0510

22-0527

22-0554

22-0574

22-0661

22-0808

22-0820

22-0875

Keyword Systems

Systems

Systems

Systems

Systems

Systems

Systems

Systems

Systems

Systems

Systems

Systems

Systems

Systems

Systems

Systems

Systems

Systems

Systems

Systems

Systems

T-Method

TB

TERF

THORP

Tank




A View of Licensee Event Reports - Relating to Nuclear Air Treatment 22-0899

A View of Licensee Event Reports - Relating to Nuclear Air Treatment 22-0899

Development of Filter Systems - Part 2, Injection Systems and Multi-Point 21-0139

Development of Filter Systems - Part 2, Injection Systems and Multi-Point 21-0139

Field Testing of Nuclear Air Treatment and Gas Processing Systems 21-0193

AG-1 Division IV, Section TB: Field Testing of Gas Processing Systems 21-0198

Iodine and NOx Behavior in the Dissolver Off-Gas and lodox Systems in 21-0271

The Difficulty of Testing Non-509 Systems to the N510 Standard 21-0318

Testing of Non-ANSYASME N509 Systems to ANSIIASME N510 2 I-0327

Testing of Non-N509 Filter Systems - Audit Experiences at McGuire 2 l-0329

Comments on Testing of Non-N509 Filter Systems - Audit Experiences at 21-0332

Field Measurement of the Performance of Air Cleaning Systems to 21-0435

US NRC Regulatory Guidance for Engineered Safety Feature Air 21-0626

The Integrated Melter Off-Gas Treatment Systems at the West Valley 23-0016

An Example of a Component Replacement when Applying ASME N509 23-0093

Value-Impact Assessment for Resolution of Generic Safety Issue 143 - 23-0380

An Introduction to the Design, Commissioning, and Operation of Nuclear 23-0439

New Challenges to Air/Gas Cleaning Systems 24-0033

Testing Cleanable/Reusable HEPA Prefilters for Mixed Waste Incinerator 24-0076

ASME N51 l-l 9xX, Standard for Periodic In-Service Testing of Nuclear Air 24-0264

Potential for HEPA Filter Damage from Water Spray Systems in Filter 24-0752

Post-Accident Air Leakage Analysis in a Nuclear Facility via T-Method 22-0374

AG-1 Division IV, Section TB: Field Testing of Gas Processing Systems 21-0198

Tritium Emissions Reduction Facility (TERF) 22-0065

The Development and Design of the Off-Gas Treatment System for the 23-0333

Radioactive Waste Tank Ventilation System Incorporating Tritium Control 24-0051

998

Keyword Tank

Tanks

Technical

Technical

Technical

Technologies

Technologies

Technology

Technology

Temperature

Temperature

Temperature

Term

Term

Term

Terms

Terms

Terms

Terms

Terms

Testing

Theory

Thermal

Thermal

Tools

Tracer

24th DOE/NRC NUCLEAR AIR CLEANING AND TREtqTf/IENT CONFERENCE


Title






Air Cleaning Technologies for the Management and Disposal of

Further Development of the Cleanable Steel HEPA Filter and Comparison


Adaptation of Nuclear Filtration Technology to the Demilitarization of

The Effects of Temperature on HEPA Filter Media





Kinetic Modelling of the Purging of Activated Carbon After Short Term






Section TA Acceptance Testing, Draft Revision 03/06/96

Filtration Theory Using Computer Simulations




Replacement Tracer Agent for the In-Place Leak Testing of Adsorbers in

999


21-0831

21-0247

21-0385

2 I-0424

2 I-0028

24-0708

22-0808

21-0419

22-0327

22-0617

21-0918

22-0736

22-0464

2 I-0662

22-0734

22-0742

22-0362

22-0732

23-0488

24-0203

24-0485

23-0333

24-047 1

22-0808

22-0698


Keyword Tracer

Tracer

Tracer

Tracers

Tracking

Trading

Transport Activated Charcoal Beds for Passive Mitigation of the Radioactivity

Trapping Dissolution Off-Gas Characterization at the Marcoule Pilot Facility: Iodine 22-0053

Treatment

Treatment

Tritiated

Tritium

Tritium

Tritium

Turbulent

U.S.

UK

Uncertainty

Underground

Unfiltered

Unfinished

Uniformity

Units

Update

Update

Uranium



Control Room Inleakage Testing Using Tracer Gases at Zion Generating 22-0830

Leak Testing of Bubble-Tight Dampers Using Tracer Gas Techniques 23-0391

Unit Vent Airflow Measurements Using a Tracer Gas Technique 24-0147

New Injection System for a Short Mixing of Test Aerosols and Gas 2 I-0080

Bar Coded Air Sample Tracking: How It Can Assist in Compliance with 23-0670

Application of Innovative Policies for Controlling Radionuclide Releases: 24-0040

22-0428

ASME N51 I-19xX, Standard for Periodic In-Service Testing of Nuclear Air 24-0264

The First Twenty Years of the ASME Committee on Nuclear Air and Gas 24-0807

Treatment of Tritiated Exhaust Gases at the Tritium Laboratory Karlsruhe 23-0365

Tritium Emissions Reduction Facility (TERF) 22-0065

Treatment of Tritiated Exhaust Gases at the Tritium Laboratory Karlsruhe 23-0365

Radioactive Waste Tank Ventilation System Incorporating Tritium Control 24-0051

Aerosol Deposition In Bends with Turbulent Flow 24-0441

Changes to Licensing for U.S. Nuclear Power Plants 22-0341

Developments in the Area of Regulatory Matters in the UK 21-0977

Uncertainty In-Place Filter Test Results 24-0676

Development of a Computer Code to Predict a Ventilation Requirement 24-0065

Control Room Envelope Unfiltered Air Inleakage Test Protocols 24-0400

Keynote Address: Nuclear Aerosols: Unfinished Business 24-0005

Effects of Filter Housing and Ductwork Configuration on Air Flow 22-0205

The Application of HEPA Filter Units in Gas Streams of High Dust 22-0540

An Update: DOP Replacement in Testing Machines for Filters and 22-0146

Radiological Health Effects Models for Nuclear Power Plant Accident 21-0057

A Thick Homogeneous Vegetated Cover Design Proves Cost- and 24-0118

1000



Title Keyword Utility

Validation

Validation

Value-Impact

Variable

Vegetated

Velocity

Vent

Ventilating

Ventilating

Ventilation

Ventilation

Ventilation

Ventilation

Ventilation

Ventilation

Ventilation

Ventilation

Ventilation

Ventilation

Ventilation

Ventilation

Ventilation/Chilled

Venting

Venting

Venting





Variable Pattern Contamination Control Under Positive Pressure


A General Correlation of MPPS Penetration as a Function of Face

Unit Vent Airflow Measurements Using a Tracer Gas Technique

A View of Licensee Event Reports - Relating to Nuclear Air Treatment


Challenges Within Ventilation Systems During Accident Situations

Application of High-Efficiency Metal Fiber Filters in Ventilation Systems of

Design and Characteristics of Annulus Ventilation and HVAC System for

New Injection System for a Short Mixing of Test Aerosols and Gas

Impacts of the Filter Clogging on the Behaviour of a Ventilation Network in


An Example of a Component Replacement when Applying ASME N509





ASME N51 l-l 9xX, Standard for Periodic In-Service Testing of Nuclear Air


Effect of Filtering at Containment Venting on the Consequences for the



1001


22-0808

24-0683

23-0380

24-0428

24-0118

24-0698

24-0147

22-0899

24-047 1

22-05 10

22-0574

22-0791

21-0080

21-0815

2 I-0844

23-0093

23-0404

23-0784

24-0051

24-0065

24-0264

21-0526

22-0753

22-0443

2 l-0876

Keyword Venting

Venting

Venting

Vents

Vessels

View

Vitreous

Vitrification

Volatile

WAK

WAK

WAK

WAK

WIPP

WIPP

Wakes

Walk-In

Wall

War

Waste

Waste

Waste

Waste

Waste

Waste

Waste



Title


lnvestigtions into the Design of a Filter System for PWR Containment




A View of Licensee Event Reports - Relating to Nuclear Air Treatment

Chronic Inhalation Studies of Man-Made Vitreous Fibers








The Influence of Salt Aerosol on Alpha Radiation Detection by WIPP

Alternatives to Current Procedures Used to Estimate Concentrations in



Development of an Air Cleaning System for Dissolving High Explosives

Global Change and the Practice for Airborne Waste Treatment


DOE Waste Management Program-Current and Future

Canadian Waste Management Program

Behavior and Control of Ruthenium During Operation of the New Waste

Steps Towards the Minimization of Particulate Emissions From a

IAEA Decadal Activities in the Field of Radioactive Gaseous Waste


21-0898

21-0933

24-0683

24-0778

22-0899

22-0191

22-0253

22-0244

22-0075

21-0222

24-0609

24-0618

22-0262

24-0188

21-0714

21-0360

22-0402

24-0089

22-0004

22-0253

22-0716

2 I-0042

2 I-0467

21-0510

21-0635

1002

Keyword Waste

Waste

Waste

Waste

Wastes

Wastes

Wastes

Water

Water

Water

Water

Water

Water-Vapour

Weapons

Welcome

Welcome

Welding

Welding

West Valley

Winds

Worst

YGN

Zion



Title





Air Cleaning Technologies for the Management and Disposal of



Behavior of the Loaded Polygonal HEPA Filter Exposed to Water Droplets


Behavior of the Polygonal HEPA Filter Exposed to Water Droplets Carried




Adaptation of Nuclear Filtration Technology to the Demilitarization of

Welcome and Objectives of the Conference

Welcome and Objectives of the Conference

Effects on the Efficiency of Activated Carbon on Exposure to Welding

Effects of Welding Fumes on Nuclear Air Cleaning System Carbon

The Integrated Melter Off-Gas Treatment Systems at the West Valley

Changing Winds in NRC’s Regulatory Environment


Application of ASME Code AG-1 to YGN 3 & 4 Plants, South Korea



24-0065

24-0076

24-0683

21-0028

21-0488

23-0138

22-0534

2 l-0526

2 I-0772

23-0380

24-0752

22-0428

21-0419

22-0003

2 I-0002

23-0639

24-0525

23-0016

21-0343

2 I-0435

22-0223

22-0830

1003

-._,“-.- .-

-. . ..-

NRC FORM 336 U.& NUCLEAR REGULATORY COMMISSION 1, REPORT NlJh@ER

P-w (A~l#nod by NRC, Add Vol., Supp.. Rw., NRCM 1102. m,3202 BIBLIOGRAPHIC DATA SHEET and Addendum Numbof& It my.)

(swiMbvctimumth8lwuw) NUREG/CP-0153

2. TITLE AND SUBTITLE CONF-960715

Proceedings of the 24th DOE/NRC Nuclear Air Cleaning and Treatment Conference 3. DATE REPORT PUBLISHED

MoNlH YEAR

Held in Portland, Oregon August 1997 July 15-18, 1996 4. FIN OR GRANT NUMBER

G6543 5. AUTHOR(S) 6. TYPE DF REPORT

M. W. First, Editor Conference Proceeding

7. PERIOD COVERED @%&a Deba)

B.PERFDRMNGDRGANiZATlDN -NAMEANDADDRESS(ri~?~pmvikiwiaiqch7iacr~&~1, U.S. Nudw~~cOmmiuairn~,~~-;lanhclrr. ptWi&Ml?l.udtMWJ-.)

Harvard School of Public Health 665 Huntingtown Avenue Boston, MA 02115-6021

8. SPONSORING DRGANUATION - NAME AND ADDRESS (rr NRC type am u abwot %cwhctw pwia NRC owbn, cwb Q t?wgim, U.S. NU&U ~ubimy cumm~im, and nviiing eddma.)

U.S. Department of Energy International Society of Nuclear Air Treatment Technologies, Inc. Washington, DC 20585 Batavia, OH 45103 U.S. Nuclear Regulatory Commission Harvard School of Public Health

Washington, DC 20555-0001 Boston, MA 02115 IO. SUPPLEMENTARY NOTES

R. Lee, NRC Project Manager Il.ABSTl?ACT(a~~wodrahaa)

This report contains the papers presented at the 24th DOE/NRC Nuclear Air Cleaning and Treatment Conference and the associated discussions. Major topics are: (1) nuclear air cleaning issues, (2) waste management, (3) instrumentation and measurement, (4) testing air and gas cleaning systems, (5) progress and challenges in cleaning up Hanford, (6) international nuclear programs, (7) standardized test methods, (8) HVAC. (9) decommissioning, (10) computer modeling applications, (1 I ) iodine treatment, (12) filters, and (13) codes and standards for filters and adsorbers.

I?. KEY WORDS/DESCRIPTORS @iat wcda aptnsu that winutiat -ban in hxdhp the mput.) 13. AVAlLABlLlTY STATEMENT

Nuclear Air Cleaning Nuclear Codes and Standards unlimited

HEPA Filters Computer Modeling 14. SECURrPl CUSSIFICATDN

Activated Carbon Adsorption (This prosl Aerosols Radioiodine unclassified Nuclear Waste Management Decontamination and Decommissioning Fdm-0

unclassified 15. NUMBER DF PAGES

16. PRlCE

tic.,. =*-.a e-c ,e D.-h

Federal Recycling Program

Documents

Proceedings of the 24th DOE/NRC Nuclear Air Cleaning and ... · PDF fileKWOC INDEX ON CONFERENCE TITLES Title Revision of Reactor Accident Source Terms and Implications for Nuclear