10 CFR Appendix I to Part 110, Illustrative List of Reprocessing Plant Components Under NRC Export Licensing Authority

Appendix I to Part 110 - Illustrative List of Reprocessing Plant Components Under NRC Export Licensing Authority
Note:

Reprocessing irradiated nuclear fuel separates plutonium and uranium from intensely radioactive fission products and other transuranic elements. Different technical processes can accomplish this separation. However, over the years Purex has become the most commonly used and accepted process. Purex involves the dissolution of irradiated nuclear fuel in nitric acid, followed by separation of the uranium, plutonium, and fission products by solvent extraction using a mixture of tributyl phosphate in an organic diluent.

Purex facilities have process functions similar to each other, including: Irradiated fuel element chopping, fuel dissolution, solvent extraction, and process liquor storage. There may also be equipment for thermal denitration of uranium nitrate, conversion of plutonium nitrate to oxide metal, and treatment of fission product waste liquor to a form suitable for long term storage or disposal. However, the specific type and configuration of the equipment performing these functions may differ between Purex facilities for several reasons, including the type and quantity of irradiated nuclear fuel to be reprocessed and the intended disposition of the recovered materials, and the safety and maintenance philosophy incorporated into the design of the facility. A plant for the reprocessing of irradiated fuel elements includes the equipment and components which normally come in direct contact with and directly control the irradiated fuel and the major nuclear material and fission product processing streams.

(1) Irradiated fuel element chopping machines.

Remotely operated equipment especially designed or prepared for use in a reprocessing plant and intended to cut, chop, or shear irradiated nuclear fuel assemblies, bundles, or rods. This equipment breaches the cladding of the fuel to expose the irradiated nuclear material to dissolution. Especially designed metal cutting shears are the most commonly employed, although advanced equipment, such as lasers, may be used.

(2) Dissolvers.

Critically safe tanks (e.g., small diameter, annular, or slab tanks) especially designed or prepared for use in a reprocessing plant, intended for dissolution of irradiated nuclear fuel and which are capable of withstanding hot, highly corrosive liquid, and which can be remotely loaded and maintained.

Dissolvers normally receive the chopped-up spent fuel. In these critically safe vessels, the irradiated nuclear material is dissolved in nitric acid and the remaining hulls removed from the process stream.

(3) Solvent extractors and solvent extraction equipment.

Especially designed or prepared solvent extractors such as packed or pulse columns, mixer settlers, or centrifugal contactors for use in a plant for the reprocessing of irradiated fuel. Solvent extractors must be resistant to the corrosive effect of nitric acid. Solvent extractors are normally fabricated to extremely high standards (including special welding and inspection and quality assurance and quality control techniques) out of low carbon stainless steels, titanium, zirconium, or other high quality materials.

Solvent extractors both receive the solution of irradiated fuel from the dissolvers and the organic solution which separates the uranium, plutonium, and fission products. Solvent extraction equipment is normally designed to meet strict operating parameters, such as long operating lifetimes with no maintenance requirements or adaptability to easy replacement, simplicity of operation and control, and flexibility for variations in process conditions.

(4) Chemical holding or storage vessels.

Especially designed or prepared holding or storage vessels for use in a plant for the reprocessing of irradiated fuel. The holding or storage vessels must be resistant to the corrosive effect of nitric acid. The holding or storage vessels are normally fabricated of materials such as low carbon stainless steels, titanium or zirconium, or other high quality materials. Holding or storage vessels may be designed for remote operation and maintenance and may have the following features for control of nuclear criticality:

(i) Walls or internal structures with a boron equivalent of at least 2 percent, or

(ii) A maximum diameter of 175 mm (7 in) for cylindrical vessels, or

(iii) A maximum width of 75 mm (3 in) for either a slab or annular vessel.

(5) Neutron measurement systems for process control.

Neutron measurement systems especially designed or prepared for integration and use with automated process control systems in a plant for the reprocessing of irradiated fuel elements. These systems involve the capability of active and passive neutron measurement and discrimination in order to determine the fissile material quantity and composition. The complete system is composed of a neutron generator, a neutron detector, amplifiers, and signal processing electronics.

The scope of this entry does not include neutron detection and measurement instruments that are designed for nuclear material accountancy and safeguarding or any other application not related to integration and use with automated process control systems in a plant for the reprocessing of irradiated fuel elements.

(6) Plutonium nitrate to plutonium oxide conversion systems. Complete systems especially designed or prepared for the conversion of plutonium nitrate to plutonium oxide, in particular adapted so as to avoid criticality and radiation effects and to minimize toxicity hazards.

(7) Plutonium metal production systems. Complete systems especially designed or prepared for the production of plutonium metal, in particular adapted so as to avoid criticality and radiation effects and to minimize toxicity hazards.

(8) Process control instrumentation specially designed or prepared for monitoring or controlling the processing of material in a reprocessing plant.

(9) Any other components especially designed or prepared for use in a reprocessing plant or in any of the components described in this appendix.

[ 79 FR 39297, July 10, 2014]

This is a list of United States Code sections, Statutes at Large, Public Laws, and Presidential Documents, which provide rulemaking authority for this CFR Part.

This list is taken from the Parallel Table of Authorities and Rules provided by GPO [Government Printing Office].

It is not guaranteed to be accurate or up-to-date, though we do refresh the database weekly. More limitations on accuracy are described at the GPO site.


United States Code
U.S. Code: Title 5 - GOVERNMENT ORGANIZATION AND EMPLOYEES
U.S. Code: Title 22 - FOREIGN RELATIONS AND INTERCOURSE
U.S. Code: Title 42 - THE PUBLIC HEALTH AND WELFARE

§ 2071 - Determination of other material as special nuclear material; Presidential assent; effective date

§ 2073 - Domestic distribution of special nuclear material

§ 2074 - Foreign distribution of special nuclear material

§ 2077 - Unauthorized dealings in special nuclear material

§ 2092 - License requirements for transfers

§ 2093 - Domestic distribution of source material

§ 2094 - Foreign distribution of source material

§ 2095 - Reports

§ 2111 - Domestic distribution

§ 2112 - Foreign distribution of byproduct material

§ 2133 - Commercial licenses

§ 2134 - Medical, industrial, and commercial licenses

§ 2139 - Component and other parts of facilities

§ 2139a - Regulations implementing requirements relating to licensing for components and other parts of facilities

§ 2141 - Licensing by Nuclear Regulatory Commission of distribution of special nuclear material, source material, and byproduct material by Department of Energy

§ 2151 - Effect of international arrangements

§ 2152 - Policies contained in international arrangements

§ 2153 - Cooperation with other nations

§ 2153a - Approval for enrichment after export of source or special nuclear material; export of major critical components of enrichment facilities

§ 2153b - Export policies relating to peaceful nuclear activities and international nuclear trade

§ 2153c - Renegotiation of agreements for cooperation

§ 2153d - Authority to continue agreements for cooperation entered into prior to March 10, 1978

§ 2153e - Protection of environment

§ 2153e-1

§ 2153f - Savings clause; Nuclear Non-Proliferation Act of 1978

§ 2154 - International atomic pool

§ 2155 - Export licensing procedures

§ 2155a - Regulations establishing Commission procedures covering grant, suspension, revocation, or amendment of nuclear export licenses or exemptions

§ 2156 - Criteria governing United States nuclear exports

§ 2156a - Regulations establishing levels of physical security to protect facilities and material

§ 2157 - Additional export criterion and procedures

§ 2158 - Conduct resulting in termination of nuclear exports

§ 2159 - Congressional review procedures

§ 2160 - Subsequent arrangements

§ 2160a - Review of Nuclear Proliferation Assessment Statements

§ 2160b - Authority to suspend nuclear cooperation with nations which have not ratified the Convention on the Physical Security of Nuclear Material

§ 2160c - Consultation with Department of Defense concerning certain exports and subsequent arrangements

§ 2160d - Further restrictions on exports

§ 2201 - General duties of Commission

§ 2231 - Applicability of administrative procedure provisions; definitions

§ 2232 - License applications

§ 2233 - Terms of licenses

§ 2234 - Inalienability of licenses

§ 2236 - Revocation of licenses

§ 2237 - Modification of license

§ 2239 - Hearings and judicial review

§ 2243 - Licensing of uranium enrichment facilities

§ 2273 - Violation of sections

§ 2282 - Civil penalties

§ 5841 - Establishment and transfers

U.S. Code: Title 44 - PUBLIC PRINTING AND DOCUMENTS
Statutes at Large

Title 10 published on 10-May-2017 03:48

The following are ALL rules, proposed rules, and notices (chronologically) published in the Federal Register relating to 10 CFR Part 110 after this date.

  • 2015-12-01; vol. 80 # 230 - Tuesday, December 1, 2015
    1. 80 FR 74974 - Miscellaneous Corrections
      GPO FDSys XML | Text
      NUCLEAR REGULATORY COMMISSION
      Final rule.
      This rule is effective December 31, 2015.
      10 CFR Parts 1, 2, 4, 7, 9, 11, 15, 19, 20, 21, 25, 26, 30, 32, 37, 40, 50, 51, 52, 55, 60, 61, 62, 63, 70, 71, 72, 73, 74, 76, 81, 95, 100, 110, 140, 150, 170, and 171