iTeh StandardsiTeh Standards
EURUSD
Your shopping cart is empty.
ASTM

ASTM E1297-96

(Test Method)

Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium

Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium

SCOPE
1.1 This test method describes procedures for measuring reaction rates by the activation reaction 93Nb(n,n`)93mNb.
1.2 This activation reaction is useful for monitoring neutrons with energies above approximately 0.5 MeV and for irradiation times up to about 30 years.
1.3 With suitable techniques, fast-neutron reaction rates for neutrons with energy distribution similar to fission neutrons can be determined in fast-neutron fluences above about 1016cm-2. In the presence of high thermal-neutron fluence rates (>1012cm-2[dot] -1), the transmutation of 93mNb due to neutron capture should be investigated. In the presence of high-energy neutron spectra such as are associated with fusion and spallation sources, the transmutation of 93mNb by reactions such as (n,2n) may occur and should be investigated.
1.4 Procedures for other fast-neutron monitors are referenced in Practice E261.
1.5 Fast-neutron fluence rates can be determined from the reaction rates provided that the appropriate cross section information is available to meet the accuracy requirements.
1.6 The values stated in SI units are to be regarded as the standard.
1.7 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

General Information

Status
Historical
Publication Date
31-Dec-1995
ICS
27.120.01 - Nuclear energy in general
Technical Committee
E10 - Nuclear Technology and Applications
Drafting Committee
E10.05 - Nuclear Radiation Metrology
Current Stage
Ref Project

Relations

Replaced By
ASTM E1297-02 - Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium
Effective Date
10-Jun-2002

Buy Standard

ASTM E1297-96 - Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of NiobiumASTM E1297-96 - Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium
PreviousNext
Standard
ASTM E1297-96 - Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium
English language
6 pages
sale 15% off
Preview
sale 15% off
Preview

Standards Content (Sample)

Designation: E 1297 – 96
Standard Test Method for
Measuring Fast-Neutron Reaction Rates by Radioactivation
1
of Niobium
This standard is issued under the fixed designation E 1297; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (e) indicates an editorial change since the last revision or reapproval.
1. Scope E 261 Practice for Determining Neutron Fluence Rate, Flu-
3
ence, and Spectra by Radioactivation Techniques
1.1 This test method describes procedures for measuring
93 93m
E 262 Test Method for Determining Thermal Neutron Re-
reaction rates by the activation reaction Nb(n,n8) Nb.
3
action and Fluence Rates by Radioactivation Techniques
1.2 This activation reaction is useful for monitoring neu-
E 844 Guide for Sensor Set Design and Irradiation for
trons with energies above approximately 0.5 MeV and for
3
Reactor Surveillance, E706 (IIC)
irradiation times up to about 30 years.
E 944 Practice for Application of Neutron Spectrum Adjust-
1.3 With suitable techniques, fast-neutron reaction rates for
3
ment Methods in Reactor Surveillance
neutrons with energy distribution similar to fission neutrons
E 1005 Test Method for Application and Analysis of Radio-
can be determined in fast-neutron fluences above about
16 −2
metric Monitors for Reactor Vessel Surveillance, E706
10 cm . In the presence of high thermal-neutron fluence rates
3
12 −2 −1 93m
(IIIA)
(>10 cm ·s ), the transmutation of Nb due to neutron
E 1006 Practice for Analysis and Interpretation of Physics
capture should be investigated. In the presence of high-energy
3
Dosimetry Results for Test Reactors, E706 (II)
neutron spectra such as are associated with fusion and spalla-
93m
E 1018 Guide for Application of ASTM Evaluated Cross
tion sources, the transmutation of Nb by reactions such as
Section Data File (ENDF/A)—Cross Section and Uncer-
(n,2n) may occur and should be investigated.
3
tainty File, E706 (IIB)
1.4 Procedures for other fast-neutron monitors are refer-
enced in Practice E 261.
3. Terminology
1.5 Fast-neutron fluence rates can be determined from the
3.1 Definitions—The definitions stated in Terminology
reaction rates provided that the appropriate cross section
E 170 are applicable to this test method.
information is available to meet the accuracy requirements.
1.6 The values stated in SI units are to be regarded as the
4. Summary of Test Method
standard.
4.1 High purity niobium is irradiated in a neutron field
1.7 This standard does not purport to address all of the
93m 93 93m
producing radioactive Nb from the Nb(n,n8) Nb reac-
safety concerns, if any, associated with its use. It is the
tion. The metastable state decays to the ground state by the
responsibility of the user of this standard to establish appro-
virtual emission of 30 keV gamma rays that are all internally
priate safety and health practices and determine the applica-
converted giving rise to the actual emission of orbital electrons
bility of regulatory limitations prior to use.
followed by X rays.
4.2 Sources of the irradiated niobium are prepared for X ray
2. Referenced Documents
or liquid scintillation counting.
2.1 ASTM Standards:
93m
2 4.3 The X rays emitted as a result of the decay of Nb are
D 1193 Specification for Reagent Water
counted, and the reaction rate, as defined in Practice E 261, is
E 170 Terminology Relating to Radiation Measurements
3 calculated from the decay rate and irradiation conditions.
and Dosimetry
4.4 The neutron fluence rate may then be calculated from
E 181 Test Methods for Detector Calibration and Analysis
3 the appropriate spectral-weighted neutron activation cross
of Radionuclides
section as defined by Practice E 261.
E 185 Practice for Conducting Surveillance Tests for Light-
3
Water Cooled Nuclear Power Reactor Vessels, E706 (IF)
5. Significance and Use
5.1 Refer to Practice E 261 for a general discussion of the
1
determination of decay rates, reaction rates, and neutron
This test method is under the jurisdiction of ASTM Committee E-10 on Nuclear
4
Technology and Applications and is the direct responsibility of Subcommittee
fluence rates with threshold detectors (1-29). Refer to Practice
E10.05 on Nuclear Radiation Metrology.
Current edition approved Jan. 10, 1996. Published March 1996. Originally
published as E 1297 – 89. Last previous edition E 1297 – 89.
2 4
Annual Book of ASTM Standards, Vol 11.01. The boldface numbers in parentheses refer to the list of references at the end of
3
Annual Book of ASTM Standards, Vol 12.02. this test method.
Copyright © ASTM, 100 Barr Harbor Drive, West Conshohocken, PA 19428-2959, United States.
1

---------------------- Page: 1 ----------------------
E 1297
E 1006 and Guide E 1018 for the use and application of results and quality control of neutron dosimeters.
obtained by this test method.
6.2 There are some distinct advantages and limi
...

Questions, Comments and Discussion

Ask us and Technical Secretary will try to provide an answer. You can facilitate discussion about the standard in here.

This May Also Interest You

ASTM
ASTM E2216-02(2020)(Guide)
Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning

SIGNIFICANCE AND USE
4.1 This standard guide applies to concrete that is still in place with a defined geometry and known, documented history.  
4.2 It is not intended for use on concrete that has already been rubbelized where it is difficult to measure the radiation levels and not easy to remove surface contamination to reduce radiation levels after concrete has been rubbelized.  
4.3 This standard guide applies to surface or volumetrically contaminated concrete, where the depth of contamination can be measured or estimated based on the history of the concrete.  
4.4 This standard guide does not apply to the reinforcement bar (rebar) found in concrete. Although most concrete contains rebar, it is generally removed before the concrete is dispositioned. In addition, rebar may be activated, and is covered under procedures for reuse of scrap metal.  
4.5 General unit-dose and unit-cost data to support the calculations is provided in the appendices of this standard guide. However, if site-specific data is available, it should be used instead of the general information provided here.  
4.6 This standard guide helps determine estimated doses to the public during disposal of concrete and to future residents of disposal areas. It does not include dose to radiation workers already involved in a radiation control program. It is assumed that the dose to radiation workers is already tracked and kept within acceptable levels through a radiation control program. The cost and dose to radiation workers could be added in to find an overall cost and dose for each option.
SCOPE
1.1 This standard guide defines the process for developing a strategy for dispositioning concrete from nuclear facility decommissioning. It outlines a 10-step method to evaluate disposal options for radioactively contaminated concrete. One of the steps is to complete a detailed analysis of the cost and dose to nonradiation workers (the public); the methodology and supporting data to perform this analysis are detailed in the appendices. The resulting data can be used to balance dose and cost and select the best disposal option. These data, which establish a technical basis to apply to release the concrete, can be used in several ways: (1) to show that the release meets existing release criteria, (2) to establish a basis to request release of the concrete on a case-by-case basis, (3) to develop a basis for establishing release criteria where none exists.  
1.2 This standard guide is based on the “Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Sites,” (1)2 from which the analysis methodology and supporting data are taken.  
1.3 Guide E1760 provides a general process for release of materials containing residual amounts of radioactivity. In addition, Guide E1278 provides a general process for analyzing radioactive pathways. This standard guide is intended for use in conjunction with Guides E1760 and E1278, and provides a more detailed approach for the release of concrete.  
1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

  • Guide
    15 pages
    English language
    sale 15% off
ASTM
ASTM E1034-95(2020)(Specification)
Standard Specification for Nuclear Facility Transient Worker Records

ABSTRACT
This specification covers the required content and provides retention requirements for records needed for in-processing of nuclear facility transient workers. This specification is not intended to cover specific skills records (such as equipment operating licenses, ASME inspection qualifications, or welding certifications), nor does it reduce any regulatory requirement for records retention at a licensed nuclear facility. Rather, the records shall contain data elements for the following information: worker identification; occupational external radiation exposure; occupational internal radiation exposure; lifetime occupational radiation exposure history; security screening; medical approval; and radiation worker training.
SIGNIFICANCE AND USE
4.1 The standardization of nuclear facility transient worker records will provide the individual transient worker with a greater assurance that the radiation doses that may be received are within regulatory limits.  
4.2 This specification establishes a fixed content for nuclear facility transient worker records. Standardizing the content of these records will facilitate interfacing with industry-wide record keeping systems, such as the Nuclear Energy Institute (NEI) Personnel Data System (PADS).  
4.3 The standardization of nuclear facility transient worker records will reduce the time required for in-processing of these workers.
SCOPE
1.1 This specification covers the required content and provides retention requirements for records needed for in-processing of nuclear facility transient workers.  
1.2 This specification applies to records to be used for in-processing only.  
1.3 This specification is not intended to cover specific skills records (such as equipment operating licenses, ASME inspection qualifications, or welding certifications).  
1.4 This specification doesPresident Barack Obama eulogy at John Lewis funeral not reduce any regulatory requirement for records retention at a licensed nuclear facility.  
Note 1: Nuclear facilities operated by the U.S. Department of Energy (DOE) are not licensed by the U.S. Nuclear Regulatory Commission (NRC), nor are other nuclear facilities that may come under the control of the U.S. Department of Defense (DOD) or individual agreement states. The references in this specification to licensee, the U.S. NRC Regulatory Guides, and Title 10 of the U.S. Code of Federal Regulations are to imply appropriate alternative nomenclature with respect to DOE, DOD, or agreement state nuclear facilities. This distinction does not alter the required content of records needed for in-processing of nuclear facility transient workers.
Note 2: This specification does not define the form of the required worker records (such as a passport or central computerized record keeping system).  
1.5 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

  • Technical specification
    5 pages
    English language
    sale 15% off
ASTM
ASTM E1297-18(Test Method)
Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium

SIGNIFICANCE AND USE
5.1 Refer to Practice E261 for a general discussion of the determination of decay rates, reaction rates, and neutron fluence rates with threshold detectors (1-29).3 Refer to Practice E1006, Practice E185 and Guide E1018 for the use and application of results obtained by this test method.(30-32)  
5.2 The half-life of  93mNb is 16.1 (2)4 years5(34) and has a K X-ray emission probability of 0.11442 ± 3.356 % per decay (35). The Kα and Kβ X-rays of niobium are at 16.521–16.615 and 18.607–18.9852 keV, respectively (35). The recommended  93Nb(n,n′)93mNb cross section comes from the International Reactor Dosimetry and Fusion File (IRDFF version 1.05, cross section compendium (36), and is shown in Fig. 1. This nuclear data evaluation is part of the Russian Reactor Dosimetry File (RRDF), cross section evaluations (37). The nuclear decay data referenced here are not taken from the latest dosimetry recommended database (33) but are selected to be consistent with the nuclear data used in the recommended IRDFF evaluation.
FIG. 1 RRDF/IRDFF-1.05 Cross Section Versus Energy for the  93Nb(n,n′) 93mNb Reaction  
5.3 Chemical dissolution of the irradiated niobium to produce very low mass-per-unit area sources is an effective way to obtain consistent results. The direct counting of foils or wires can produce satisfactory results provided appropriate methods and interpretations are employed. It is possible to use liquid scintillation methods to measure the niobium activity provided the radioactive material can be kept uniformly in solution and appropriate corrections can be made for interfering activities.  
5.4 The measured reaction rates can be used to correlate neutron exposures, provide comparison with calculated reaction rates, and determine neutron fluences. Reaction rates can be determined with greater accuracy than fluence rates because of the current uncertainty in the cross section versus energy shape.  
5.5 The  93Nb(n,n′)93mNb reaction has the desirable properties o...
SCOPE
1.1 This test method describes procedures for measuring reaction rates by the activation reaction  93Nb(n,n′) 93mNb.  
1.2 This activation reaction is useful for monitoring neutrons with energies above approximately 0.5 MeV and for irradiation times up to about 48 years (three half-lives), provided that the analysis methods described in Practice E261 are followed.  
1.3 With suitable techniques, fast-neutron reaction rates for neutrons with energy distribution similar to fission neutrons can be determined in fast-neutron fluences above about 1016 cm−2. In the presence of high thermal-neutron fluence rates (>1012cm−2·s−1), the transmutation of  93mNb due to neutron capture should be investigated. In the presence of high-energy neutron spectra such as are associated with fusion and spallation sources, the transmutation of 93mNb by reactions such as (n,2n) may occur and should be investigated.  
1.4 Procedures for other fast-neutron monitors are referenced in Practice E261.  
1.5 Fast-neutron fluence rates can be determined from the reaction rates provided that the appropriate cross section information is available to meet the accuracy requirements.  
1.6 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.7 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.8 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

  • Standard
    7 pages
    English language
    sale 15% off
  • Standard
    7 pages
    English language
    sale 15% off
ASTM
ASTM D3843-16(2021)e1(Practice)
Standard Practice for Quality Assurance for Protective Coatings Applied to Nuclear Facilities

SIGNIFICANCE AND USE
4.1 Quality assurance, as covered by this practice, comprises all those planned and systematic actions necessary to provide adequate confidence that safety-related coating work in nuclear facilities as defined in Guide D5144, will perform satisfactorily in service.  
4.2 It is not practical to impose all the requirements of this practice on certain specific items that require only a small quantity of coating material. The licensee, consistent with his formal Quality Assurance Program, may accept affidavits of compliance or certification attesting to the quality of a shop or field coating for such items. If required by licensing commitment; safety-related coatings that are not qualified or for which the quantification basis is indeterminate as defined in Guide D5144, shall be identified, quantified, and documented.  
4.3 This practice may be incorporated in a project specification by direct reference or may be used to provide guidelines for the quality assurance program for coatings, on the basis of the licensee’s requirements. Effective use of this practice may also require the incorporation of applicable sections in project specifications for coatings on concrete, steel, equipment, and other related items.
SCOPE
1.1 This standard replaces ANSI N101.4 and provides a common basis for, and specifically comprises quality assurance requirements applicable to, safety-related protective coating work in Coating Service Level I areas of nuclear facilities as defined in Guide D5144.  
1.2 This standard meets the requirements of ANSI N101.4 while also recognizing advancements in technology and industry practices since transfer to ASTM responsibility for updating, rewriting, and issuing replacement standards to ANSI N101.4.  
1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

  • Standard
    18 pages
    English language
    sale 15% off
ASTM
ASTM C1210-21(Guide)
Standard Guide for Establishing a Measurement System Quality Control Program for Analytical Chemistry Laboratories Within Nuclear Industry

SIGNIFICANCE AND USE
4.1 A laboratory quality assurance program is an essential program for laboratories within the nuclear industry. Guide C1009 provides guidance for establishing a quality assurance program for an analytical laboratory within the nuclear industry. This guide deals with the control of measurements aspect of the laboratory quality assurance program. Fig. 1 shows the relationship of measurement control with other essential aspects of a laboratory quality assurance program.
FIG. 1 Quality Assurance of Analytical Laboratory Data  
4.2 The fundamental purposes of a measurement control program are to provide the with-use  assurance (real-time control) that a measurement system is performing satisfactorily and to provide the data necessary to quantify measurement system performance. The with-use  assurance is usually provided through the satisfactory analysis of quality control samples (reference value either known or unknown to the analyst). The data necessary to quantify measurement system performance is usually provided through the analysis of quality control samples or the duplicate analysis of process samples, or both. In addition to the analyses of quality control samples, the laboratory quality control program should address (1) the preparation and verification of standards and reagents, (2) data analysis procedures and documentation, (3) calibration and calibration procedures, (4) measurement method qualification, (5) analyst qualification, and (6) other general program considerations. Other elements of laboratory quality assurance also impact the laboratory quality control program. These elements or requirements include (1) chemical analysis procedures and procedure control, (2) records storage and retrieval requirements, (3) internal audit requirements, (4) organizational considerations, and (5) training/qualification requirements. To the extent possible, this standard will deal primarily with quality control requirements rather than overall quality assurance re...
SCOPE
1.1 This guide provides guidance for establishing and maintaining a measurement system quality control program. Guidance is provided for general program considerations, preparation of quality control samples, analysis of quality control samples, quality control data analysis, analyst qualification, measurement system calibration, measurement method qualification, and measurement system maintenance.  
1.2 This guidance is provided in the following sections:    
Section  
General Quality Control Program Considerations  
5  
Quality Control Samples  
6  
Analysis of Quality Control Samples  
7  
Quality Control Data Analysis  
8  
Analyst Qualification  
9  
Measurement System Calibration  
10  
Qualification of Measurement Methods and Systems  
11  
Measurement System Maintenance  
12  
1.3 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

  • Guide
    7 pages
    English language
    sale 15% off
  • Guide
    7 pages
    English language
    sale 15% off
ASTM
ASTM C1009-21(Guide)
Standard Guide for Establishing and Maintaining a Quality Assurance Program for Analytical Laboratories Within the Nuclear Industry

SIGNIFICANCE AND USE
4.1 The mission of an analytical laboratory is to provide quality analyses on nuclear fuel cycle materials. An analytical laboratory QA program is comprised of planned and systematic actions needed to provide confidence that this mission is conducted in an acceptable and consistent manner.  
4.2 The analytical laboratories involved in the analysis of nuclear fuel cycle materials are required to implement a documented QA program. Regulatory agencies may mandate some form of control requirements for all or a part of a laboratory's operation. A documented QA program is also necessary for those laboratory operations required to comply with ASME NQA-1 or ISO/IEC 17025, or the requirements of many accreditation bodies. Even when not mandated, laboratory QA programs should be established as a sound and scientific technical practice. This guide provides guidance for establishing and maintaining a QA program to control those analytical operations vital to ensuring the quality of chemical analyses.  
4.3 Quality assurance programs are designed and implemented by organizations to assure that the quality requirements for a process, product or service will be fulfilled. The quality system is complementary to technical requirements that may be specific to a process or analytical method. Each laboratory should identify applicable program requirements and use standards to implement a quality program that meets the appropriate requirement. This guide may be used to develop and implement an analytical laboratory QA program. Other useful implementation standards and documents are listed in Section 2 and Appendix X1.  
4.4 The guides for QA in the analytical laboratory within the nuclear fuel cycle have been written to provide guidance for each of the major activities in the laboratory and are displayed in Fig. 1. The applicable standard for each subject is noted in the following sections.  
FIG. 1 Essential Elements of Analytical Laboratory Quality Assurance System  
4.5 Althoug...
SCOPE
1.1 This guide covers the establishment and maintenance of a quality assurance (QA) program for analytical laboratories within the nuclear industry. References to key elements of ASME NQA-1 and ISO/IEC 17025 provide guidance to the functional aspects of analytical laboratory operations. When implemented as recommended, the practices presented in this guide will provide a comprehensive QA program for the laboratory. The practices are grouped by functions, which constitute the basic elements of a laboratory QA program.  
1.2 The essential, basic elements of a laboratory QA program appear in the following order:    
Section  
Organization  
5  
Quality Assurance Program  
6  
Training and Qualification  
7  
Procedures  
8  
Laboratory Records  
9  
Control of Records  
10  
Management of Customer Requests and Commitments to Customers  
11  
Control of Procurement  
12  
Control of Measuring Equipment and Materials  
13  
Control of Measurements  
14  
Control of Nonconforming Work  
15  
Candidate Actions  
16  
Preventative Actions  
17  
1.3 Collection of samples and associated sampling procedures are outside the scope of this guide. The user may refer to sampling practices developed by Subcommittee C26.02.  
1.4 Nuclear laboratories are required to handle a variety of hazardous materials, including but not limited to radioactive samples and materials. The need for proper handling of these materials is discussed in 13.2.4. While this guide focuses on the nuclear laboratory QA program, proper handling of nuclear materials is essential for proper function of the QA program.  
1.5 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Tra...

  • Guide
    12 pages
    English language
    sale 15% off
  • Guide
    12 pages
    English language
    sale 15% off
ASTM
ASTM E2216-02(2020)(Guide)
Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning

SIGNIFICANCE AND USE
4.1 This standard guide applies to concrete that is still in place with a defined geometry and known, documented history.  
4.2 It is not intended for use on concrete that has already been rubbelized where it is difficult to measure the radiation levels and not easy to remove surface contamination to reduce radiation levels after concrete has been rubbelized.  
4.3 This standard guide applies to surface or volumetrically contaminated concrete, where the depth of contamination can be measured or estimated based on the history of the concrete.  
4.4 This standard guide does not apply to the reinforcement bar (rebar) found in concrete. Although most concrete contains rebar, it is generally removed before the concrete is dispositioned. In addition, rebar may be activated, and is covered under procedures for reuse of scrap metal.  
4.5 General unit-dose and unit-cost data to support the calculations is provided in the appendices of this standard guide. However, if site-specific data is available, it should be used instead of the general information provided here.  
4.6 This standard guide helps determine estimated doses to the public during disposal of concrete and to future residents of disposal areas. It does not include dose to radiation workers already involved in a radiation control program. It is assumed that the dose to radiation workers is already tracked and kept within acceptable levels through a radiation control program. The cost and dose to radiation workers could be added in to find an overall cost and dose for each option.
SCOPE
1.1 This standard guide defines the process for developing a strategy for dispositioning concrete from nuclear facility decommissioning. It outlines a 10-step method to evaluate disposal options for radioactively contaminated concrete. One of the steps is to complete a detailed analysis of the cost and dose to nonradiation workers (the public); the methodology and supporting data to perform this analysis are detailed in the appendices. The resulting data can be used to balance dose and cost and select the best disposal option. These data, which establish a technical basis to apply to release the concrete, can be used in several ways: (1) to show that the release meets existing release criteria, (2) to establish a basis to request release of the concrete on a case-by-case basis, (3) to develop a basis for establishing release criteria where none exists.  
1.2 This standard guide is based on the “Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Sites,” (1)2 from which the analysis methodology and supporting data are taken.  
1.3 Guide E1760 provides a general process for release of materials containing residual amounts of radioactivity. In addition, Guide E1278 provides a general process for analyzing radioactive pathways. This standard guide is intended for use in conjunction with Guides E1760 and E1278, and provides a more detailed approach for the release of concrete.  
1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

  • Guide
    15 pages
    English language
    sale 15% off
ASTM
ASTM C992-20a(Specification)
Standard Specification for Boron-based Neutron Absorbing Material Systems for Use in Nuclear Fuel Storage Racks in Pool Environment

ABSTRACT
This specification defines essential criteria for all material combinations in boron-based neutron-absorbing material systems used for nuclear spent fuel storage racks in nuclear light water reactors, spent-fuel assemblies, or disassembled components. The boron-based neutron absorbing materials normally consist of metallic boron or a boron-containing boron compound supported by a matrix of aluminum, steel, or other materials. Material systems covered in this specification should always be capable of maintaining a B10 areal density that can support the required subcriticality depending on the design specification for service life.
SCOPE
1.1 This specification defines criteria for boron-based neutron absorbing material systems used in racks in a pool environment for storage of nuclear light water reactor (LWR) spent-fuel assemblies or disassembled components to maintain sub-criticality in the storage rack system.  
1.2 Boron-based neutron absorbing material systems normally consist of metallic boron or a chemical compound containing boron (for example, boron carbide, B4C) supported by a matrix of aluminum, steel, or other materials.  
1.3 In a boron-based absorber, neutron absorption occurs primarily by the boron-10 isotope that is present in natural boron to the extent of 18.3 ± 0.2 % by weight (depending upon the geological origin of the boron). Boron enriched in boron-10 could also be used.  
1.4 The materials systems described herein shall be functional (that is, always be capable to maintain a boron-10 areal density such that subcriticality is maintained depending on the design specification for the service life in the operating environment of a nuclear spent fuel pool).  
1.5 Observance of this specification does not relieve the user of the obligation to conform to all applicable international, national, and local regulations.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

  • Technical specification
    4 pages
    English language
    sale 15% off
  • Technical specification
    4 pages
    English language
    sale 15% off
ASTM
ASTM E1034-95(2020)(Specification)
Standard Specification for Nuclear Facility Transient Worker Records

ABSTRACT
This specification covers the required content and provides retention requirements for records needed for in-processing of nuclear facility transient workers. This specification is not intended to cover specific skills records (such as equipment operating licenses, ASME inspection qualifications, or welding certifications), nor does it reduce any regulatory requirement for records retention at a licensed nuclear facility. Rather, the records shall contain data elements for the following information: worker identification; occupational external radiation exposure; occupational internal radiation exposure; lifetime occupational radiation exposure history; security screening; medical approval; and radiation worker training.
SIGNIFICANCE AND USE
4.1 The standardization of nuclear facility transient worker records will provide the individual transient worker with a greater assurance that the radiation doses that may be received are within regulatory limits.  
4.2 This specification establishes a fixed content for nuclear facility transient worker records. Standardizing the content of these records will facilitate interfacing with industry-wide record keeping systems, such as the Nuclear Energy Institute (NEI) Personnel Data System (PADS).  
4.3 The standardization of nuclear facility transient worker records will reduce the time required for in-processing of these workers.
SCOPE
1.1 This specification covers the required content and provides retention requirements for records needed for in-processing of nuclear facility transient workers.  
1.2 This specification applies to records to be used for in-processing only.  
1.3 This specification is not intended to cover specific skills records (such as equipment operating licenses, ASME inspection qualifications, or welding certifications).  
1.4 This specification doesPresident Barack Obama eulogy at John Lewis funeral not reduce any regulatory requirement for records retention at a licensed nuclear facility.  
Note 1: Nuclear facilities operated by the U.S. Department of Energy (DOE) are not licensed by the U.S. Nuclear Regulatory Commission (NRC), nor are other nuclear facilities that may come under the control of the U.S. Department of Defense (DOD) or individual agreement states. The references in this specification to licensee, the U.S. NRC Regulatory Guides, and Title 10 of the U.S. Code of Federal Regulations are to imply appropriate alternative nomenclature with respect to DOE, DOD, or agreement state nuclear facilities. This distinction does not alter the required content of records needed for in-processing of nuclear facility transient workers.
Note 2: This specification does not define the form of the required worker records (such as a passport or central computerized record keeping system).  
1.5 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

  • Technical specification
    5 pages
    English language
    sale 15% off
ASTM
ASTM D8157-19(Guide)
Standard Guide for Qualification Testing of Coatings Used in Coating Service Level I in Nuclear Power Plants

SIGNIFICANCE AND USE
4.1 This guide presents concise guidance and approach to developing a test document for qualifying a coating for CSLI service, whether a new or existing coating. Guidance for evaluating existing qualification test data for applicability is presented in Guide D8104.  
4.2 The requirements for qualification testing can be found in Quality Assurance Criteria III (Design Control), IX (Control of Special Processes), and XI (Test Control) of 10 CFR 50, Appendix B, as implemented, respectively, by Requirements III, IX, and XI of NQA-1. A test document developed per this guide is intended to be compliant with these requirements.  
4.3 This guide implements the guidance provided in Guide D5144 for qualification of coatings for use in CSLI service. Additional guidance is provided in Regulatory Guide 1.54, Revisions 0 through 3, as may be invoked by the licensee.  
4.4 For plants with a license basis that predates the requirements of ANSI N5.12 and N101.2, this guide also is applicable. For these plants, the coatings or coating systems may be designated as acceptable, rather than qualified.  
4.5 All qualification testing shall comply with the licensee’s approved quality assurance program.
SCOPE
1.1 This guide provides an approach to identifying the need for and development of a test document to qualify coatings for Coating Service Level I (CSLI) service in nuclear power plants.  
1.2 It is the intent of this guide to provide a recommended basis for establishing a coatings qualification test document, not to mandate a singular basis for all test documents. Variations or simplifications of the process described in this guide may be appropriate for any given operating or new construction nuclear power plant depending on its licensing commitments.  
1.3 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard.  
1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.5 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

  • Guide
    4 pages
    English language
    sale 15% off