Regulatory Guide 5.5: Difference between revisions
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{{#Wiki_filter:U.S. ATOMIC ENERGY COMMISSION | {{#Wiki_filter:2101r3 U.S. ATOMIC ENERGY COMMISSION | ||
REGULATORY | REGULATORY GL IDE | ||
DIRECTORATE OF REGULATORY STANDARDS | |||
OF REGULATORY | REGULATORY GUIDE 5.5 STANDARD METHODS FOR CHEMICAL, MASS SPECTROMETRIC. | ||
STANDARDS | |||
REGULATORY | |||
GUIDE 5.5 STANDARD METHODS FOR CHEMICAL, MASS SPECTROMETRIC. | |||
AND SPECTROCHEMICAL | AND SPECTROCHEMICAL ANALYSIS OF | ||
ANALYSIS OF NUCLEAR-GRADE | NUCLEAR-GRADE URANIUM DIOXIDE POWDERS AND PELLETS | ||
URANIUM DIOXIDE POWDERS AND PELLETS | |||
==A. INTRODUCTION== | ==A. INTRODUCTION== | ||
Paragraph | oxygen-uranium atomic ratio to verify stoichiometry, for verification of isotopic uranium composition, and for Paragraph 70.22(b) of 10 CFR Part 70, "Special various impurities such as carbbn, chloride, fluoride, Nuclear Material," requires an applicant for a license to moisture, nitrogen, sulfur, and trace elements. This possess certain quantities of speciad nuclear material in standard was approved by the ASTM on March 3, 1972, an unsealed form to describe, among other things, his and published in May 1972 with the designation C | ||
70.22(b) of 10 CFR Part 70, "Special Nuclear Material," requires an applicant for a license to possess certain quantities of speciad nuclear material in an unsealed form to describe, among other things, his procedures for control of and accounting for such material. | procedures for control of and accounting for such 696-72.' | ||
material. This guide identifies acceptable methods for chemical, isotopic, and impurity analysis which an | |||
==C. REGULATORY POSITION== | |||
applicant may specify as part of his procedures for accounting for special nuclear material. The analytical methods for the measurement of nuclear-grade uranium dioxide powders and pellets | |||
==B. DISCUSSION== | ==B. DISCUSSION== | ||
Committee C-26 on Fuel, Control, and Moderator Materials for Nuclear Reactor Applications of the American Society for Testing and Materials (ASTM) has developed a standard containing some methods for the analytical chemical analysis of nuclear-grade uranium dioxide powders and pellets | contained in ASTM Standard C 696-72, "Standard Methods for Chemical, Mass Spectrometric, and Committee C-26 on Fuel, Control, and Moderator Spectrochemical Analysis of Nuclear-Grade Uranium Materials for Nuclear Reactor Applications of the Dioxide Powders and Pellets," are generally acceptable American Society for Testing and Materials (ASTM) has and provide an adequate basis for the assay, isotopic developed a standard containing some methods for the measurement, and impurity analysis of nuclear-grade analytical chemical analysis of nuclear-grade uranium uranium dioxide powders and pellets. | ||
dioxide powders and pellets. These methods cover the analysis for uranium content by a titrimetric and gravimetric method to be used for uranium dioxide of 'Copies my be obtained from the Amuerean Socity for varying impurity levels and sample sizes, for Testing and Materials, 1916 Race St., Philadelphia. Pa. 19103. | |||
U EC REGULATORY GUIDE$ dmA UofYo tile I US. Alomic -mEmpgobtaid ma by req Wapse. | |||
Cowulen. m OC.dobleu | |||
2U. | |||
Rpustory Guides we imuad to demcribe and mgke "milod to the public Atetmlak: Okaeror o a Swnl* Comuof mid toemgus 1w nailthoc abble to ldo AEC Ragulatesrv stafl of nma seific pars gl " lOiIproitnomU In Onom mifdt m ~wwsuread aW haMd be sent to go @alaoSine Waduls . D.C. 20M4. | |||
Okaeror o a Comuof mid toemgus 1w nailthoc abble to ldo AEC Ragulatesrv stafl of nma | |||
In Onom mifdt m ~wwsuread aW | |||
to dWia udmchniclua maued by the eta" in of film Cn- I ', o. U.S. Atomic Energv Comndmei. | trw Comrmnsmen's regulutions. to dWia udmchniclua maued by the eta" in of film Cn- I ',o. U.S. Atomic Energv Comndmei. | ||
wi ptll fIn c p-oblawn or ostulted oneWesd . or to wopwid gumbnin "" | |||
Chiel. Public Promiinp Stoa | M Attontion: Chiel. Public Promiinp Stoa. | ||
1. Pow Reactors | impns. Raillv Guid as not -akuIte for ralleliefs and tonpiim wlk "tem ir ni t rnquired Methods aMd tolitomsff met ffrm them at gut in The pT1 we kmm In the lfoll, 0 tSn broa dWeaons: | ||
sh @e well km acoolibbe if tlay Would@ a basi for tm findings requniste to the .isuarm or ominuanm of a pmrm* or kc~ by thw CommissIon. 1. Pow Reactors | |||
===7. Trausportation === | ===6. Prouct=== | ||
3 Fues mci Melteria Facilities a. Occupo:stonl t"em | 2. Resasrch and Tes Rheactors | ||
===7. Trausportation=== | |||
3 Fues mci Melteria Facilities a. Occupo:stonl t"em kr rmd dl riod alro y. , a ippropriate, to accuol u mts 4. Enwironiental end Siting 9. Antitruat wsur Pubalsted g6&s "it be S. a*l*mkS sad Plant Prtecllon 10. General comnenints o-d to reflect now infor*ntion or esnvarm.}} | |||
{{RG-Nav}} | {{RG-Nav}} |
Latest revision as of 06:24, 24 November 2019
ML003739552 | |
Person / Time | |
---|---|
Issue date: | 02/09/1973 |
From: | Office of Nuclear Regulatory Research |
To: | |
References | |
RG-5.5 | |
Download: ML003739552 (1) | |
2101r3 U.S. ATOMIC ENERGY COMMISSION
REGULATORY GL IDE
DIRECTORATE OF REGULATORY STANDARDS
REGULATORY GUIDE 5.5 STANDARD METHODS FOR CHEMICAL, MASS SPECTROMETRIC.
AND SPECTROCHEMICAL ANALYSIS OF
NUCLEAR-GRADE URANIUM DIOXIDE POWDERS AND PELLETS
A. INTRODUCTION
oxygen-uranium atomic ratio to verify stoichiometry, for verification of isotopic uranium composition, and for Paragraph 70.22(b) of 10 CFR Part 70, "Special various impurities such as carbbn, chloride, fluoride, Nuclear Material," requires an applicant for a license to moisture, nitrogen, sulfur, and trace elements. This possess certain quantities of speciad nuclear material in standard was approved by the ASTM on March 3, 1972, an unsealed form to describe, among other things, his and published in May 1972 with the designation C
procedures for control of and accounting for such 696-72.'
material. This guide identifies acceptable methods for chemical, isotopic, and impurity analysis which an
C. REGULATORY POSITION
applicant may specify as part of his procedures for accounting for special nuclear material. The analytical methods for the measurement of nuclear-grade uranium dioxide powders and pellets
B. DISCUSSION
contained in ASTM Standard C 696-72, "Standard Methods for Chemical, Mass Spectrometric, and Committee C-26 on Fuel, Control, and Moderator Spectrochemical Analysis of Nuclear-Grade Uranium Materials for Nuclear Reactor Applications of the Dioxide Powders and Pellets," are generally acceptable American Society for Testing and Materials (ASTM) has and provide an adequate basis for the assay, isotopic developed a standard containing some methods for the measurement, and impurity analysis of nuclear-grade analytical chemical analysis of nuclear-grade uranium uranium dioxide powders and pellets.
dioxide powders and pellets. These methods cover the analysis for uranium content by a titrimetric and gravimetric method to be used for uranium dioxide of 'Copies my be obtained from the Amuerean Socity for varying impurity levels and sample sizes, for Testing and Materials, 1916 Race St., Philadelphia. Pa. 19103.
U EC REGULATORY GUIDE$ dmA UofYo tile I US. Alomic -mEmpgobtaid ma by req Wapse.
Cowulen. m OC.dobleu
2U.
Rpustory Guides we imuad to demcribe and mgke "milod to the public Atetmlak: Okaeror o a Swnl* Comuof mid toemgus 1w nailthoc abble to ldo AEC Ragulatesrv stafl of nma seific pars gl " lOiIproitnomU In Onom mifdt m ~wwsuread aW haMd be sent to go @alaoSine Waduls . D.C. 20M4.
trw Comrmnsmen's regulutions. to dWia udmchniclua maued by the eta" in of film Cn- I ',o. U.S. Atomic Energv Comndmei.
wi ptll fIn c p-oblawn or ostulted oneWesd . or to wopwid gumbnin ""
M Attontion: Chiel. Public Promiinp Stoa.
impns. Raillv Guid as not -akuIte for ralleliefs and tonpiim wlk "tem ir ni t rnquired Methods aMd tolitomsff met ffrm them at gut in The pT1 we kmm In the lfoll, 0 tSn broa dWeaons:
sh @e well km acoolibbe if tlay Would@ a basi for tm findings requniste to the .isuarm or ominuanm of a pmrm* or kc~ by thw CommissIon. 1. Pow Reactors
6. Prouct
2. Resasrch and Tes Rheactors
7. Trausportation
3 Fues mci Melteria Facilities a. Occupo:stonl t"em kr rmd dl riod alro y. , a ippropriate, to accuol u mts 4. Enwironiental end Siting 9. Antitruat wsur Pubalsted g6&s "it be S. a*l*mkS sad Plant Prtecllon 10. General comnenints o-d to reflect now infor*ntion or esnvarm.