ASHRAE 90365-1993 Heating Ventilating and Air-Conditioning Design Guide for Department of Energy Nuclear Facilities《能源部门的核设施的供暖 通风 空调设计指南》.pdf
《ASHRAE 90365-1993 Heating Ventilating and Air-Conditioning Design Guide for Department of Energy Nuclear Facilities《能源部门的核设施的供暖 通风 空调设计指南》.pdf》由会员分享,可在线阅读,更多相关《ASHRAE 90365-1993 Heating Ventilating and Air-Conditioning Design Guide for Department of Energy Nuclear Facilities《能源部门的核设施的供暖 通风 空调设计指南》.pdf(75页珍藏版)》请在麦多课文档分享上搜索。
1、ASHRAE DG-L 73 0757b50 050bL00 073 I d Heating, Ventilating, and Air-Conditioning DESIGN GUIDE DEPARTMENT OF ENERGY NUCLEAR FACILITIES American Society of Heating, Refrigerating and Air-Conditioning Engineers, Inc. ASHRAE DG-L 93 0759b50 050bLOL T2T I Heating, Ventilafng, and Air-Conditioning DESIGN
2、 GUIDE for DEPARTMENT OF ENERGY NUCLEAR FACILITIES ASHRAE DG-I, 73 m 0759650 0506202 966 I Heating, Ventilating, and Air-Conditioning DESIGN GUIDE for DEPARTMENT OF ENERGY NUCLEAR FACILITIES American Society of Heating, Refrigerating and Air-conditioning Engineers, Inc. ASHRAE DG-L 73 0759b50 050bL0
3、3 AT2 I ISBN 1-88341 3-03-6 Copyright 1993 American Society of Heating, Refrigerating and Air-Conditioning Engineers, Inc. 1791 Tullie Circle N.E. Atlanta, GA 30329-2305 Printed in the United States of America iv ASHRAE DG-L 93 0759b50 05ObLOY 739 I TABLE OF CONTENTS Sectionflitle Page Foreword vii
4、1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 Confinement System Classification 1 Confinement System Differential Pressures . 5 Air Lock Design 8 System Monitoring Capability . 14 Pitot Tube Test Ports . 20 Nuclear Facility Air Change Requirements . 24 Glovebox Fire Suppression . 27 Filter Selection . 28 Redu
5、ndancy Requirements 32 Control Systems 34 Pressure Gauge Installation . 39 Glovebox Airflow Instrumentation . 46 Enclosure Face Velocity Requirements 53 Fire/Smoke Protection of HEPA Filters . 56 Glovebox Ventilation Design 64 V ASHRAE DG-L 73 0757650 0506105 h75 I FOREWORD The purpose of the Heatin
6、g, Ventilating, and Air-Conditioning WAC) Design Guide for Department of Energy POE) Nuclear Facilities is to help ensure consistency in establishing the design basis for HVAC systems serving such facilities. Any design for DOE facilities must fulfill the requirements stated in DOE Order 6430.1 A, G
7、eneral Design Criteria. However, the order references many documents, such as ERDA 76-21, Nuclear Air Cleaning Handbook; NRC Regulatory Guides; and the ACGIH Industrial Ventilation Manual. Order 6430.lA also has many void areas with respect to HVAC design that have generated confusion and inconsiste
8、nt application of sound HVAC principles. This design guide is a document that combines applicable information from all of these resources to provide HVAC guidance for the design engineer. The intent of this document is to not only state the Department of Energys design requirements for HVAC systems,
9、 but also to express some of the engineering judgment used in designing the systems. This design guide was developed by members of ASHRAE TC 9.2, Industrial Air Conditioning, Subcommittee on Nuclear Facilities. The information in each section was obtained from researching DOE orders, technical docum
10、ents, and site procedures and from discussions with experienced personnel at DOE sites. This document should be used by design agencies, liaison groups, health protection organizations, and other persons or groups involved in the design, installation, and operation of HVAC systems. The use of this d
11、ocument is most effective when preparing design criteria for a project. By incorporating the appropriate sections of this design guide in this phase, the document can provide the design agency with appropriate HVAC system design parameters that will fulfill the needs of the customer and satisfy code
12、 and regulatory requirements. Although this document is considered a design guide, it should be understood that the information presented reflects both the current DOE requirements and the generally accepted requirements with respect to HVAC. However, the responsibility for satisfying applicable cod
13、es and regulations remains with the designer. All new project installations and future modifications should consider these design guidelines. vii ASHRAE DG-2 93 0757b50 05ObLOb 502 I SECTION 1 CONFINEMENT SYSTEM CLASSIFICATION GENERAL HVAC systems in nuclear facilities must be designed to confine tr
14、ansferable radioactive contamination within specific controlled building areas in the event of an accidental release, spill, or system failure. As required by DOE Order 6430.1A, three confinement systems are used to achieve this objective: primary confinement, secondary confinement, and tertiary con
15、finement. Before any HVAC system design can begin, the building areas must be analyzed on a case- by-case basis to determine the ventilation system requirements for the confine- ment. Using ERDA 76-21, Nuclear Air Cleaning Handbook, as a guide is very helpful. With the guidance of the Handbook, conf
16、inement areas, called zones, must be established throughout the building based on the level of hazard in the areas. The zone classification determines the ventilation and architectural requirements that the confinement system) must meet. After the zones have been established, the ventilation system
17、is designed to maintain a prescribed differential pressure between various zones. CONFINEMENT SYSTEM DEFINITIONS The following confinement system descriptions are typical for a plutonium facility confinement system and conform to DOE Order 6430.1A. The order also contains confinement system descript
18、ions for specific facilities, such as tritium facilities. At least one of the confinements must be designed to withstand design- basis accidents, such as a tornado. This is normally documented in the facilitys safety analysis report (SAR). Primary Confinement The primary confinement system consists
19、of barriers, enclosures, gloveboxes, piping, vessels, tanks, glovebox exhaust ductwork, primary confinement HEPA filter plenums, etc., whose principal function is to prevent the release of hazardous material to areas other than where process operations are normally 1 ASHRAE DG-L 73 m 0757650 0506307
20、 448 I conducted. Unavoidable breaches in the primary confinement barrier must be compensated for by provision of adequate inflow of air or safe collection of spilled material. The exhaust ventilation system must be sized to ensure adequate inflow of air in the event of the largest credible breach o
21、f confinement. This level of confinement is used when radioactive materials or contamination is present during normal operations. Secondary Confinement The secondary confinement system consists of the walls, floors, roofs, and associated ventilation systems that confine any potential release of haza
22、rdous materials from primary confinement. This system typically includes the operating area boundary and the ventilation system serving the operating area. The ventilation system is designed to ensure proper airflow direction and velocity in the event of the largest credible breach in the barrier. P
23、enetrations of the secondary confinement barrier typically require positive seals to prevent migration of contamination out of the secondary confinement area. This level of confinement is used when a space could become contaminated from an abnormal event. Tertiary Confinement The tertiary confinemen
24、t consists of the walls, floor, roof, and associated exhaust system of the process facility. It is the final barrier to release of hazardous material to the environment. This level of confinement is used when a space is never expected to become contaminated. CONFINEMENT SYSTEM CLASSIFICATION To dete
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