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F75 放射性三廢處理 標準查詢與下載



共找到 56 條與 放射性三廢處理 相關(guān)的標準,共 4

Radiation Solid Waste Cave Disposal Safety Regulations

ICS
13.280
CCS
F75
發(fā)布
2024-11-28
實施
2025-01-01

本標準規(guī)定了以水泥為主要固化(固定)介質(zhì)的低水平放射性廢物包特性鑒定要求和方法。 本標準適用于待近地表處置的低水平放射性廢物包(包括固化體和固定體)的特性鑒定。 本標準不適用于使用高完整性容器的廢物包的特性鑒定。

Characterization of low level radioactive waste packages—Cemented waste

ICS
13.030.30
CCS
F75
發(fā)布
2022-12-29
實施
2023-01-01

本標準規(guī)定了低、中水平放射性廢物固化體(以下簡稱水泥固化體)的最低性能要求和檢驗方法。 本標準適用于近地表處置的水泥固化體,大體積水泥澆注固化體除外。

Performance requirements for low and intermediate level radioactive waste form-Cemented waste form

ICS
CCS
F75
發(fā)布
2011-02-18
實施
2011-09-01

本標準規(guī)定了放射性廢物的產(chǎn)生、收集、預(yù)處理、處理、整備、運輸、貯存、處置與排放等各個階段以及退役和環(huán)境整治等有關(guān)活動的管理目標和基本要求。 本標準適用于核燃料循環(huán)各環(huán)節(jié)和核技術(shù)應(yīng)用與鈾、釷伴生礦開發(fā)利用所產(chǎn)生的放射性廢物的管理。其他實踐所產(chǎn)生的放射性廢物的管理亦可參照執(zhí)行。

Regulations for radioactive waste management

ICS
27.120.99
CCS
F75
發(fā)布
2002-08-05
實施
2003-04-01

本標準規(guī)定了低、中水平放射性固體廢物(以下簡稱“廢物”)近地表處置時,廢物接收的基本要求、接收準則和質(zhì)量保證。 本標準適用于所有向上地表處置場發(fā)送的廢物,其中主要是核電廠、核燃料循環(huán)和核設(shè)施退役所產(chǎn)生的廢物。對放射性同位素生產(chǎn)和應(yīng)用中所產(chǎn)生的廢物也應(yīng)參照執(zhí)行。

Acceptance criteria for near surface disposal of radioactive waste

ICS
13:030
CCS
F75
發(fā)布
1997-07-30
實施
1998-09-01

本標準規(guī)定了低、中水平放射性廢物瀝青固化體(以下簡稱瀝青固化體)的最低性能要求和檢驗方法。 本標準適用于近地表處置的瀝青固化體,巖洞處置的瀝青固化體也可參照執(zhí)行。

Characteristic requirements for solidified waste of low-and intermediate-level radioactive waste--Bitumen solidified waste

ICS
27.120.30
CCS
F75
發(fā)布
1995-12-13
實施
1996-08-01

本標準規(guī)定了低、中水平放射性廢物塑料固化體的最低性能要求和檢驗方法。 本標準適用于近地表處置的塑料固化體,巖洞處置的塑料固化體也可參照使用。

Characteristic requirements for solidified waste of low and intermediate level radioactive waste. Plastic solidified waste

ICS
13.280
CCS
F75
發(fā)布
1993-08-06
實施
1994-07-01

本標準規(guī)定了低、中水平放射性廢物水泥固化體(以下簡稱水泥固化體)的最低性能要求和檢驗方法。 本標準適用于近地表處置的水泥固化體,巖洞處置的水泥固化體也可參照執(zhí)行。

Characteristic requirements for solidified waste of low and intermediate level radioactive waste. Cement solidified waste

ICS
13.280
CCS
F75
發(fā)布
1993-08-06
實施
1994-07-01

本標準規(guī)定了低中水平放射性固體廢物巖洞處置場的選址、設(shè)計、建造、運行、關(guān)閉和監(jiān)督及其安全分析與環(huán)境影響評價的基本要求。 本標準適用于在廢礦井、現(xiàn)有人工洞室、天然洞以及專門為處置廢物而挖掘的巖洞中的廢物處置。

Regulations for disposal of solid low-and intermediate level radioactive wastes in rock cavities

ICS
13.030
CCS
F75
發(fā)布
1992-08-19
實施
1993-04-01

本標準規(guī)定了高水平放射性廢液貯存廠房工藝設(shè)計所涉及的各方面的要求。 本標準適用于乏燃料后處理產(chǎn)生的高水平放射性廢液及其濃縮液貯存廠房設(shè)計。對放射性濃度相當和含有多種長壽命放射性核素廢液的貯存設(shè)施,在設(shè)計時也應(yīng)參照使用。

Regulations for designing storage building of high level radioactive liquid waste

ICS
13.300
CCS
F75
發(fā)布
1989-12-21
實施
1990-07-01

本標準規(guī)定了對低、中水平放射性固體廢物暫時貯存的要求。 本標準適用于產(chǎn)生放射性固體廢物的任何實踐中,符合低、中水平的放射性固體廢物的暫時貯存(以下簡稱“廢物暫時貯存”)。 本規(guī)定不適用于尾礦渣類放射性固體廢物的貯存管理。

Regulations for interim storage of low-and intermediate-level radioactive solid wastes

ICS
13.300
CCS
F75
發(fā)布
1989-12-21
實施
1990-07-01

本標準規(guī)定了含14C生物廢物安全管理的一般要求、特性鑒定、分類收集與包裝、暫存、運輸、預(yù)處理、處理、整備及處置等。 1.應(yīng)根據(jù)GB5085(所有部分)和HJ298對廢物進行危險廢物特性鑒定; 2.含14C生物廢物管理流程管理環(huán)節(jié)包含(特性鑒定、分類收集、暫存、運輸、預(yù)處理、處理、整備、處置)

Regulations of 14C containing biological waste management

ICS
27.120.99
CCS
F75
發(fā)布
2020-08-04
實施
2020-11-01

Technical requirements for on-site transfer devices of radioactive wet waste in nuclear power plants

ICS
13.280
CCS
F75
發(fā)布
2019-12-30
實施
2020-07-01

Requirements for decontamination of low- and medium-level radioactive solid waste by high-pressure water jetting

ICS
27.12
CCS
F75
發(fā)布
2018-01-18
實施
2018-05-01

Requirements for pretreatment of low- and intermediate-level solid waste for decommissioning production reactors

ICS
27.12
CCS
F75
發(fā)布
2018-01-18
實施
2018-05-01

Operation requirements for pyrolysis and incineration of low-level combustible solid waste

ICS
13.28
CCS
F75
發(fā)布
2018-01-18
實施
2018-05-01

αWaste pre-disposal management requirements

ICS
27.12
CCS
F75
發(fā)布
2018-01-18
實施
2018-05-01

Acceptance criteria for overpressure treatment of low- and medium-level radioactive compactable solid waste

ICS
27.12
CCS
F75
發(fā)布
2018-01-18
實施
2018-05-01

5.1 This test method can be used to provide a measure of the reactivity of a material in a dilute solution in which the test response is dominated by the dissolution or leaching of the test specimen. It can be used to compare the dissolution or leaching behaviors of candidate radioactive waste forms and to study the reactions during static exposure to dilute solutions in which solution feed-back effects can be maintained negligible, depending on the test conditions. 5.2 The test is suitable for application to natural minerals, simulated waste form materials, and radioactive waste form material specimens. 5.3 Data from this test may form part of the larger body of data that is necessary in the logical approach to long-term prediction of waste form behavior, as described in Practice C1174. In particular, measured solution concentrations and characterizations of altered surfaces may be used in the validation of geochemical modeling codes. 5.4 This test method excludes the use of crushed or powdered specimens and organic materials. 5.5 Several reference test parameter values and reference leachant solutions are specified to facilitate the comparison of results of tests conducted with different materials and at different laboratories. However, other test parameter values and leachant solution compositions can be used to characterize the specimen reactivity. 5.5.1 Tests can be conducted with different leachant compositions to simulate groundwaters, buffer the leachate pH as the specimen dissolves, or measure the common ion effect of particular solutes. 5.5.2 Tests can be conducted to measure the effects of various test parameter values on the specimen response, including time, temperature, and S/V ratio. Tests conducted for different durations and at various temperatures provide insight into the reaction kinetics. Tests conducted at different S/V ratio provide insight into chemical affinity (solution feed-back effects) and the approach to saturation. 5.6 Either aerated or deaerated solutions may be used in this test method except when testing highly radioactive specimens. Deaerated solutions are mandatory in tests conducted with highly radioactive specimens to minimize the effects of nitrogen radiolysis. Preparation of deaerated leachants is addressed in 7.2.2. 5.7 Control of the oxygen fugacity is not part of this test method. Such control and measurement may be required for specific uses of test data but are beyond the scope of this test method. 5.8 Tests can be conducted using vessels compatible with the test specimen, leachant, and test environment. Corrosion resistant materials shall be used for tests with corrosive brines. Radiation-resistant materials shall be used for tests in radiation fields wherein the accumulated absorbed dose will exceed 104 rad (see Note 1).

Standard Test Method for Static Leaching of Monolithic Waste Forms for Disposal of Radioactive Waste

ICS
13.280 ; 27.120.30
CCS
F75
發(fā)布
2017
實施

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 ± 0.28201;% 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 and health practices and determine the applicability of regulatory limitations prior to use.

Standard Specification for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Fuel Storage Racks in a Pool Environment

ICS
27.120.01
CCS
F75
發(fā)布
2016
實施



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