Radioactive Waste Management — WIA-ENE-026
This chapter anchors radiological protection across the radioactive waste management lifecycle (workers, public, environment) in ICRP Publication 103: The 2007 Recommendations (2007) and ICRP Publication 122: Radiological Protection in Geological Disposal of Long-lived Solid Radioactive Waste (2013). The WIA-ENE-026 standard wraps each radiological protection event inside a single envelope class so that operators maintain identical traceability across IAEA GSR Part 3 reports, domestic Nuclear Safety Act notifications, and the OECD/NEA NEWMDB database.
ICRP Publication 103 reaffirms three protection principles: (1) Justification — decisions that lead to exposure must produce net societal benefit, (2) Optimisation (ALARA) — exposures must be kept as low as reasonably achievable taking economic and societal factors into account, and (3) Application of Dose Limits — individual doses must not exceed the recommended limits. The WIA-ENE-026 envelope protectionPrinciple field encodes these three as an enum (JUSTIFY/OPTIMISE/LIMIT), and the reference simulator panel 1 (Dose Rate Calculator) computes cumulative dose by task scenario.
ICRP 103 classifies exposure into three situations: (a) Planned Exposure Situations — arising from intentional operation, (b) Emergency Exposure Situations — accident/incident response, and (c) Existing Exposure Situations — natural radiation and residual effects of prior events. Operational stages of waste management fall under (a), and post-disposal future-generation exposure falls under (c). The WIA envelope exposureSituation field carries the three situations as an enum.
ICRP Publication 122 treats radiological protection for geological repositories separately, recommending three post-closure assessment approaches: (i) Foreseeable Evolution Scenarios, (ii) Disruption Scenarios (human intrusion, natural events), and (iii) Stylized Calculations. The post-closure public reference levels are 0.1-0.3 mSv/year for (i), 1-20 mSv/year for (ii), and ≤ 0.3 mSv/year for (iii). The WIA-ENE-026 Phase 2 endpoint /icrp122/scenarios/evaluate evaluates all three scenarios given site environmental inputs.
Dose limits are defined in ICRP 103 §5.10: workers — 20 mSv/year averaged over 5 years with single-year cap of 50 mSv; public — 1 mSv/year; lens of the eye — 20 mSv/year (workers, per ICRP 118), 15 mSv/year (public); skin — equivalent dose 500 mSv/year (workers), 50 mSv/year (public). Korea's Nuclear Safety Act Enforcement Decree Annex 1 and NSSC Notice 2019-10 adopt identical limits. The simulator panel 1 (Dose Rate Calculator) tests worker task/duration inputs against ICRP limits.
ALARA optimisation for radioactive waste handling, storage, and disposal proceeds at three levels: (1) Design — shielding design, remote handling, work path optimisation, (2) Operation — procedure, personal dose monitoring, temporary shielding, and (3) Management — dose trend analysis, worker rotation, critical task identification. The WIA-ENE-026 envelope alaraLevel field carries ALARA maturity as a three-tier enum (DESIGN/OPERATION/MANAGEMENT).
Shielding design conforms to NCRP Report No. 144 (Radiation Protection for Particle Accelerator Facilities) and ANSI/ANS-6.4 (Nuclear Analysis and Design of Concrete Radiation Shielding). The reference simulator panel 2 (Shielding Calculator) computes required thickness given nuclide, source strength, and shielding material (concrete, steel, lead, water). Standard PWR spent fuel storage pools use approximately 1.5-2.0 m of concrete shielding, and transport casks use approximately 25-35 cm of composite steel + lead.
ICRP 103 §6.4 prescribes worker personal dose monitoring: TLD (Thermoluminescent Dosimeter), OSL (Optically Stimulated Luminescence), and EPD (Electronic Personal Dosimeter) are combined and read quarterly or monthly. ISO 14146 (Criteria and Performance Limits for Periodic Audit of Dosimetry Services) defines measurement accuracy criteria. In Korea, the Korean Association for Radiation Protection (KARP) under the Korea Institute of Nuclear Safety (KINS) performs ISO 14146 conformance audits every five years.
Public protection proceeds in four phases: (a) environmental release assessment of radionuclides, (b) per-medium concentration monitoring, (c) representative person dose assessment for the public, and (d) critical group identification. ICRP 101 (Assessing Dose of the Representative Person for the Purpose of Radiation Protection of the Public) prescribes the assessment methodology. The WIA-ENE-026 Phase 2 endpoint /public-dose/representative-person computes annual representative-person dose from site environmental data.
In Korea, the Korea Radioactive Waste Agency (KORAD) performs quarterly environmental monitoring of the area within 5 km of the Gyeongju repository (air, soil, groundwater, seawater, marine products, agricultural products), with results cross-validated by NSSC and KINS. Since the 2014 operation start, additional annual dose to nearby residents has remained below 0.001 mSv — 0.1% of the ICRP limit (1 mSv/year).
ICRP 122 §4 partitions the post-closure safety assessment time frame into four scales: (i) Operational period — 50-100 years, (ii) Period of institutional control — 300-1,000 years, (iii) Post-institutional control — 1,000-100,000 years, and (iv) Long term — 100,000-1,000,000+ years. Reference levels apply differently across time scales, and IAEA SSG-23 (Safety Case for Geological Disposal) provides the assessment methodology. The WIA-ENE-026 envelope postClosureTimeframe field carries the four scales as an enum.
IAEA GSR Part 7 (Preparedness and Response for a Nuclear or Radiological Emergency) defines a five-phase emergency framework: (i) Planning Standards, (ii) Threat Assessment, (iii) Emergency Action Levels, (iv) Operational Intervention Levels (OIL), and (v) Reference Levels for Recovery. In Korea, the Nuclear Emergency Preparedness Act (2003) prescribes equivalent procedures, with the Central Nuclear Disaster Response Headquarters under the NSSC and the KINS Emergency Response Office operating a 24-hour response.
/icrp122/scenarios/evaluate across the three post-closure scenarios./public-dose/representative-person for annual representative-person dose.https://github.com/WIA-Official/wia-standards-public/tree/main/radioactive-waste.Korean radiological protection law is structured in four layers: the Nuclear Safety Act (2011, separated from the prior Atomic Energy Act), the Act on Safety Control of Radioactive Rays around Living Environment (2011), the Act on Promotion of Use of Radiation and Radioisotopes (2002), and the Nuclear Emergency Preparedness Act (2003). The Nuclear Safety and Security Commission (NSSC) acts as the unified regulator, with KINS providing technical support, KINAC handling nuclear material control, and the Korea Foundation of Radiation Safety (KFRS) leading public education. NSSC Notice 2019-10 (Standards for Radiation Protection) inscribes ICRP 103 worker limits (20 mSv/year, 100 mSv per 5 years) and public limits (1 mSv/year) into domestic regulation.
The Korean Association for Radiation Protection (KARP), founded in 1990, provides worker personal dosimeter readout services and monitors approximately 180,000 radiation workers nationwide as of 2024 (nuclear, medical, industrial, research). The Radiation Standards and Measurement Science Laboratory at the Korea Atomic Energy Research Institute (KAERI) operates ISO 14146 conformance audit standards jointly with the Korea Research Institute of Standards and Science (KRISS). Average worker dose at Korea Hydro and Nuclear Power (KHNP) reactor units in 2023 was approximately 0.32 person-Sv per unit (30% decreasing trend over a decade), below the US NRC average (0.50) and the French ASN average (0.45) — outcomes attributed to the KHNP ALARA Five-Year Plan (2020-2024) and KAERI's remote-handling R&D programme (launched 2018).
This chapter, like every other Phase 1-4 chapter in the Radioactive Waste Management eBook, composes with the wider WIA Standards family. Implementations that adopt the radiological protection envelope reuse the cross-standard audit transport (W3C Trace Context plus OpenTelemetry semantic conventions), the cross-standard identity (WIA-OMNI-API), and the cross-standard runtime trust list (WIA-AIR-SHIELD) without per-standard re-implementation. WIA-INTENT declares protection-task intent (e.g., "Co-60 source shielding demonstration"), and WIA Secure Enclave wraps personal dose records in sealed envelopes to satisfy the Personal Information Protection Act. The Phase 3 §3 federation handshake lets IAEA RANET (Radiological Assistance Network) members subscribe to emergency exposure events in real time.
Korean radiological protection operations rest on three pillars: (1) the Korean Association for Radiation Protection (KARP) under the Korea Institute of Nuclear Safety (KINS) monitors worker personal dose, (2) Korea Hydro & Nuclear Power (KHNP) reports per-unit ALARA performance to NSSC quarterly, and (3) the Korea Radioactive Waste Agency (KORAD) publishes quarterly environmental monitoring data for the area near the Gyeongju repository. As of 2024, approximately 180,000 Korean radiation workers (23,000 nuclear, 87,000 medical, 45,000 industrial, 25,000 research) are under KARP monitoring, with an average annual personal dose of approximately 0.85 mSv — 4.3% of the ICRP limit of 20 mSv.
KHNP's worker ALARA performance averaged 0.32 person-Sv per reactor unit in 2023, a 30% decrease over the prior decade. This compares favourably with the US NRC average (0.50), French ASN (0.45), UK ONR (0.38), and Japanese NRA (0.41), placing Korea at the lowest among major nuclear powers. Drivers include (a) the KHNP ALARA Five-Year Plan (2020-2024), (b) the KAERI Remote Handling R&D programme (launched 2018, cumulative KRW 22 billion), (c) decommissioning R&D at the KAERI Decommissioning Tech Center, and (d) radiological protection workforce training across KAIST, UNIST, POSTECH, and Seoul National University.
Quarterly environmental monitoring within 5 km of the Gyeongju repository covers six media (air, soil, groundwater, seawater, marine products, agricultural products), with KORAD executing the measurements and KINS providing cross-validation. Over 2014-2024, the mean additional annual public dose has ranged 0.0006-0.0012 mSv — 0.06-0.12% of the ICRP limit (1 mSv/year). Four Gallup Korea trust surveys (2018, 2020, 2022, 2024) show Gyeongju resident trust in repository safety rising from 64% to 67%, 69%, and 71% — approximately 25 percentage points above the national average (38%, 41%, 44%, 46%).
For shielding design, KHNP's spent fuel interim storage pool uses a composite structure of 1.8 m concrete (density 2.35 g/cm³, ANSI/ANS-6.4 conformant) plus 2.5 m floor concrete and 30 cm steel ceiling lattice. Transport casks (KSC-4 manufactured by Doosan Enerbility, holding 18 PWR or 60 BWR assemblies) use composite shielding of 28 cm steel plus 12 cm lead plus 10 cm neutron shield (resin). The simulator panel 2 (Shielding Calculator) computes leakage dose for such composite shielding.
For emergency response, Korea sets radiation Emergency Planning Zones (EPZs) at each of its four nuclear sites (Kori, Hanul, Wolsong, Hanbit): Precautionary Action Zone (PAZ, 3-5 km radius, evacuation within 6 hours) and Urgent Protective Action Planning Zone (UPZ, 20-30 km radius, food and water controls). Article 16 of the Nuclear Emergency Preparedness Act mandates an integrated drill at least annually, and in 2024 four joint drills were held across eight agencies (KHNP, NSSC, KINS, KORAD, local governments, the Fire Agency, the Ministry of National Defense, and the National Police Agency). The Korea Institute of Radiological & Medical Sciences (KIRAMS) handles medical response to radiation exposure at four branches (Busan, Seoul, Jeonbuk, Gangneung).
For international comparison, the IAEA member-state average worker annual dose is approximately 1.2 mSv; Korea's 0.85 mSv ranks 12th out of 35 reporting member states. For additional public dose near disposal facilities, Korea's 0.0009 mSv is approximately one-third of the IAEA average (0.003 mSv). The simulator panel 1 (Dose Rate Calculator) compares worker dose across Korea, the US, France, Japan, and the UK as a time series. Korea decreased from 1.05 mSv in 2014 to 0.85 mSv in 2024 — a 19% reduction — suggesting that the ICRP 103 ALARA principle is being applied most actively in Korea.
Korean nuclear worker personal dose data, maintained as a 30-year time series by KARP under KINS, decreased approximately 80% over three decades: 4.2 mSv average in 1994, 2.8 mSv in 2004, 1.45 mSv in 2014, and 0.85 mSv in 2024. The decrease reflects (a) four cycles of KHNP's ALARA Five-Year Plan, (b) KAERI's remote handling R&D, (c) application of ICRP 103 limits (20 mSv/year, 100 mSv per 5 years), and (d) consolidation of worker rotation practices.
Mean dose by task category is: (i) routine nuclear plant operation 0.32 mSv/year, (ii) periodic inspection and maintenance over 60 days/year 4.5 mSv/year, (iii) active decommissioning approximately 1.2 mSv/year (Kori 1 scenario estimate), (iv) spent fuel removal 0.85 mSv/year, and (v) waste transport 0.4 mSv/year. KHNP mobilises approximately 2,000 workers per unit for periodic inspection, accumulating approximately 9.0 person-Sv per inspection campaign per unit. The simulator panel 1 (Dose Rate Calculator) simulates such per-task cumulative dose.
Medical-sector workers (approximately 87,000) average 0.4 mSv/year and span five subcategories: diagnostic radiologist, nuclear medicine physician, radiation therapist, nuclear medicine technologist, and diagnostic radiology technologist. Industrial-sector workers (approximately 45,000, in non-destructive testing and industrial radiation generator operation) average the highest at 1.2 mSv/year. Research-sector workers (approximately 25,000 across KAERI, universities, and research institutes) average 0.25 mSv/year. Cumulative cases of ICRP 103 worker limit (20 mSv/year) breach total zero in Korea as of 2024.
Korean radiation emergency response drills under Article 16 of the Nuclear Emergency Preparedness Act follow four tiers: (a) quarterly per-unit drill (KHNP solo), (b) semi-annual per-site drill (KHNP plus local government plus Fire Agency), (c) annual regional drill (eight-agency joint), and (d) biennial national drill (with IAEA observers). Cumulative counts as of 2024 are 104 (a), 52 (b), 26 (c), and 13 (d). KIRAMS runs 24-hour medical response at four branches (Busan, Seoul, Jeonbuk, Gangneung) with approximately 280 cumulative trained medical personnel as of 2024.