Central Storage Facility Research Articles

Handling Heritage Objects. Moving the Entire Pharmaceutical Collection within the National Museum of Transylvanian History

Starting with 2018, the building previously housing the History of Pharmacy Collection (a privately owned building), known as the Pharmacy Museum, underwent massive restoration. The building, also known as the Hintz House, has traditionally been housing the exhibition of pharmaceutical objects – a collection owned by the National Museum of Transylvanian History. When the building was set to be restored, the collection, which then counted around 2400 inventory numbers, was packed and moved to the headquarters of the museum in the central storage facility, where it remained until 2023. The newly reorganized permanent exhibition at the Hintz House is set to be re‑opened in early 2024. The logistics of such an activity was complicated, as it was the first complex transfer of an extensive collection that the museum had organized in the last decades. The entire collection was assessed before moving, from a conservation point of view, to establish if any objects require specific handling, along with materials and equipment for their manipulation. The collection’s relocation was intended to last for a few years; during this time, most of the cultural objects were planned to remain packed and temporarily stored since the collection needed to be moved back to Hintz House once the renovation was completed. The museum staff did the packing under the strict supervision of conservators and restorers, and a moving company specializing in art handling was hired to transport the collection to the museum headquarters.

Calculation of the Absorbed Dose by a Borosilicate Glass Matrix and its Simulated Irradiation

The state of liquid radioactive wastes (LRW) management at Ukrainian Nuclear Power Plants (NPPs) is characterized by the lack of a completed technological cycle from processing to obtaining the final product suitable for further long-term storage or disposal. As a result, the storage tanks for bottoms residue (BR) are 65-75% full (Zaporozhye and South-Ukrainian NPPs), and the resource for placing molten salt at Zaporizhzhya NPP (92.7%) is close to exhaustion [1]. Therefore, the development of technologies and materials for NPP LRW solidification is an urgent need and aims to ensure the processing of LRW to a solid state that will meet the acceptance criteria for disposal in centralized storage facilities. One of the effective methods of LRW solidification is their vitrification. The main advantage of vitrification is that during the vitrification process the volume of waste is reduced by several times and this saves expensive storage space [2, 3]. The purpose of this work is to calculate the absorbed dose that borosilicate glass matrices with included bottoms residue will accumulate over 300 years of storage, and to study the effect of simulated X-ray irradiation on their physical and mechanical properties.

Review of studies on effect of gadolinium alloying on properties of corrosion-resistant steels. Part 1. Effect of gadolinium on properties of micromelts made of corrosion-resistant steel

The effect of gadolinium on the properties of corrosion-resistant steels used to ensure nuclear safety during the temporary storage, transportation and final disposal of spent nuclear fuel is studied. It is revealed that at present there is great interest in replacing boron with gadolinium for the absorption of thermal neutrons in alloys, which is a global trend. It is established that gadolinium, being a lanthanide, has the largest thermal neutron capture cross section and, despite its high atomic mass, remains the most effective neutron absorber that can potentially ensure the nuclear safety required for temporary storage, transportation and final disposal of spent nuclear fuel. The results of analytical studies can be used as a methodological material for laying of the foundations for the widespread use of gadolinium-containing materials in advanced designs of neutron absorbers, temporary and centralized storage facilities and containers for transporting spent nuclear fuel, as well as in the construction of shields for the protection of nuclear power plants.

Performance Evaluation of Waste Management Practices at DHQ Hospital Sheikhupura

Hospital waste management (HWM) is extremely important and it is very different kind of waste that has high potential of spreading infection and diseases. There should be proper management of this waste, otherwise it can be hazardous Objective: The objective of the study is to evaluate the waste management practices at DHQ Hospital, Sheikhupura Methods: It was cross-sectional hospital-based study. The study was carried out at DHQ Hospital Sheikhupura. The sample size of the study was 169 including 94 waste handlers, 45 nurses and 30 doctors were included. Data was collected through questionnaire using non-probability convenient sampling technique, which was entered and statistically analyzed using SPSS 20.0. Results: Among 94 waste handlers, 30.8% were 21-30 years old, 64.9% males and 45.7% had up to 5 years’ work experience. 67.0% had been vaccinated, 87.2% confirmed that waste is segregated at source and100.0% waste handlers were provided with color bags for various types of hospital wastes. 92.6% stated that pre-treatment procedure is carried out before hospital waste disposal and 75.5% waste handlers were provided with protective gears. Among 45 nurses, 55.6% were 31-40 years old and 64.4% had up to five years’ work experience. 100.0% nurses ensured internal collection of waste bags & containers and their transportation to the central storage facility of hospital on the daily basis. 82.2% coordinated and monitored all the operations related to waste management and for this purpose regularly met with hospital waste management committee. 100.0% nurses recorded the waste quantities generated by the department on weekly basis. Among 30 doctors, 73.3% organized training activities for HWM staff on safe waste management procedures.

Моделювання радіаційної обстановки при поводженні з відпрацьованим ядерним паливом

We have developed a model of the technological process for handling spent nuclear fuel in the reception building of the Centralized Storage Facility for Spent Nuclear Fuel using the ChNPP VRdose Planner Pro v. 2.2DEV-0. The results of the technological process simulation proved the reliability of the virtual models for scenarios of radiation-hazardous work for the optimization of the dose loads of personnel.

Temperature effect on gypsum-bearing soil and supported (building) foundations: The case of the Central Storage Facility of Villar de Cañas, Spain

Thermal load imposed on the ground by the foundations of some singular buildings may produce variations in geochemistry conditions. In soils containing soluble salts, such as gypsum, their dissolution/precipitation rates may be modified, triggering ground settlement as well as angular distortion of building foundations. This paper examines these processes for the case of the Central Storage Facility for high-level radioactive waste planned in Spain. This facility would impose a thermal load over a long period of time due to the disposal of spent nuclear fuel. A numerical model, including the equations for describing the dissolution/precipitation process, as well as the hydrogeological, thermal, chemical, and geomechanical changes in the ground caused by the construction and operation of the facilities, is proposed. The model focuses on the response of the building foundation under different hypothesis of thermal loading underneath the building. Comsol Multiphysics software was used for solving the resulting partial differential equations by the finite element method. This analysis concludes that moderate thermal loading of the ground would develop in the Case Study, with negligible mechanical effect on the foundation. • Thermal load imposed by some buildings may produce variations in ground chemistry conditions. • A temperature dependency occurs on the dissolution processes of calcium sulfated phases. • Thermal load is expected over a long period of time due to the disposal of spent nuclear fuel. • With moderate thermal loading of the ground, negligible mechanical effect on the foundation develop.

The Shared Storage Facility in Poland: A Pilot Project of the National Institute for Museums and Public Collections (NIMOZ)

The safe storage of collections for future generations is the most important statutory activity of every museum worldwide. Although this objective is a long-held one, statistics show that, regrettably, a historical and global problem still exists in this field, including for Polish museums. Fortunately, positive changes have been implemented since the end of the 20th century, resulting not only in new infrastructure projects, but also in new approaches to the longstanding problem. Contemporary museum storage facilities are perceived not only as restricted museum spaces, but also, and primarily, as a combination of places, people and processes. Storage can therefore represent an optimum tool for museum conservation, when understood as a change management process whose purpose is to exercise conscious and real influence on the durability of collections. Importantly, this process should correspond to contemporary environmental protection practices. Then, and only then, will museums be capable of protecting cultural heritage appropriately, without increasing risks to future generations. In Poland, the National Institute for Museums and Public Collections (NIMOZ) is currently implementing an infrastructure project entitled ‘The Central Storage Facility for Museum Collections’ (CMZM), whose concept encompasses the questions and problems referred to above. In effect, a shared storage facility will be built in the suburbs of Warsaw to provide high-quality protection for collections, while employing cost-efficient construction processes and low-energy solutions while in operation. The pilot project and case study represents a model solution: one that can be followed by museum professionals planning new collection storage facilities in other regions of Poland.

Estimating gamma and neutron radiation fluxes around BWR quivers for nuclear safeguards verification purposes

Non-destructive assay (NDA) methods are at the core of nuclear safeguards verification of spent nuclear fuel (SNF). In Sweden, the spent nuclear fuel from all the reactor sites is moved to the Swedish central interim storage facility for spent nuclear fuel (for which the Swedish acronym is Clab). A new facility, Clink, is planned at the site where the SNF will undergo a safeguards verification prior to encapsulation for long-term storage. The fuel to be encapsulated includes both regular fuel assemblies as well as “non-regular” fuel assemblies including fuel objects called quivers, which are specially designed containers to house damaged or failed and leaking spent fuel rods in a way to isolate the rods from the environment and prevent contamination. The quiver concept was recently introduced in the Swedish nuclear market by Westinghouse Electric Sweden AB and it has led to some unique challenges from a safeguards verification standpoint which stem from their construction. Their overall stainless steel build, while providing robustness to the structure, also greatly diminishes the possibility of detecting gamma or neutron radiation using traditional safeguards measurement devices. The current investigation looks into the practicalities of safeguards verification of boiling water reactor (BWR) quiver objects in the spent fuel pool from above, and also assesses the possibility of their verification from the side using the widely used Fork detector. The Fork instrument has been routinely employed by both operators and inspectors around the world to verify spent fuel for routine safeguards inspections. In the present work, we model the BWR quiver and the Fork instrument in the Monte Carlo particle transport code, Serpent2 to estimate the radiation flux around the quiver objects. We have shown that the gamma and neutron radiation from the BWR quiver were heavily attenuated by the stainless steel lid and could not be relied on to make a safeguards verification from above. Furthermore, it was established that while gamma radiation from the quiver remains measurable on the sides of the quiver by the Fork instrument, the neutron counts were low compared to a typical BWR fuel assembly of similar fuel content albeit within the limits of detectability of the Fork.

A Bi-level optimization-based community energy management system for optimal energy sharing and trading among peers

The economic and environmental benefits of renewable energy have increased in significance over the past decade. Local energy markets can play a vital role in energy transition by facilitating the rapid proliferation of renewable-based energy resources, thereby increasing the renewable energy hosting capacity of the power grid. This paper proposes an energy management system for a smart locality that facilitates local energy trading involving consumers with renewable energy units, a central storage facility, and a power grid. Two optimization frameworks for sharing surplus onsite produced energy are developed here. The first framework maximizes the combined revenue of sellers and buyers, while the second, a game theoretical model, maximizes consumer utilization at the lower level and the revenue of the common storage facility at the higher level. An intensive study is carried out to investigate the benefits of energy sharing that maximizes overall revenue. The results indicate that the grid pricing scheme is a major factor that determines the revenue sharing between the central storage facility entity and the consumers. The first framework results in optimal resource allocation, while the second framework concentrates only on revenue generation. Results indicate that the energy seller profits are higher if the real-time grid prices are used and if the consumers are not charged according to their willingness to pay.

Technological Challenges & Environmental Mitigation via Bio-oil Production from Biomass Resources

Biomass is among the most promising energy source in the twenty-first century amidst the energy scenario in the global community as a carbon-neutral fuel. Climate change is a global threat to the ecosystem and will be minimized by the introduction of renewable energy into the stream of the world energy projects. This study focuses on drawbacks and prospects of the thermochemical technology such as bubbling fluidized bed, circulating fluidized bed, conical spouted bed, rotary cone, auger and ablative reactors. The challenges are complexities in scale-up of the technologies, sustainability of non - food crop and biomass residues supply, bulkiness and high moisture content, transport network to a centralized storage facility and deoxygenated catalysts development for a higher purity of bio-oil yield and stability. However, the bio-oil yield for BFB, CFB, CSB, RC, A-R and AbR are at an average of 3.52-60, 45.2-75, 9.93–70, 14.27–51.8, 21.7-53.6, 50–70 wt.% respectively. The BFB & CFB are often used, while the AbR shows the highest bio-oil yield. The most promising technology is the AbR with a high propensity of more than 70wt.% bio-oil yield. Therefore, a techno-economic analysis of the technologies of specific capacity across board be employed for equipment selection, simplified process plant; higher yield with cost-effective operation and maintenance cost etc. Global biodiesel production has been projected from (36 to 39) bln L between 2017-2027 [1] when achieved will go a long way in curtailing the effect of climate change.

Деякі проблемні питання в ядерній енергетичній галузі України

Institute for Safety Problems of Nuclear Power Plants (NPP) of the National Academy of Sciences of Ukraine at a meeting of the National Commission for Radiation Protection of Ukraine on June 1, 2020. It is described the crisis in the nuclear industry due to approval of the new energy balance for 2020 by the Ministry of Energy and Environmental Protection of Ukraine. According to this balance, the volume of electricity production by NPP decreased and at the same time the share of thermal power plants and “green energy”, which produce much more expensive electricity, increased in the energy market. The situation is analyzed and recommendations are given for the implementation of measures to improve it. It is shown that the main task of the Ukrainian energy sector will be to continue the course of market relations and to abandon excessive market regulation. Market relations will lead to the fact that generating companies with cheaper energy will be able to sell it not at the cost level price, but at tariffs that have formed in the market. The price of nuclear energy will be brought up to the level of the price of energy produced by thermal power plants. Consumption costs will increase, but government generation will receive more funds, and the state will decide where to direct them: to subsidies for the population or to the development of nuclear or renewable energy. It is proposed to make the necessary changes to the legislation on “green energy”; establish a reasonable tariff for energy produced at NPPs; to introduce technical and organizational measures to ensure the operation of NPP power units in shunting modes. It is concluded that the optimal solution for the future from the standpoint of the both environmental and economic policy of Ukraine is the gradual replacement of NPP power units, which have “exhausted” project resource, with modern new ones with a higher level of safety. This will support the share of NPPs in the energy balance of Ukraine at 40−50%, as well as contribute to the fulfillment of its commitments to increase the use of low-carbon technologies in energy. As for solving energy problems of Ukraine on the basis of promising technologies — small modular reactors (SMR), this strategy does not yet have a proper feasibility study and is not confirmed by the necessary proven practice, as in the world such reactors are still being developed. Observations on the construction of the Central Spent Fuel Storage Facility (CSFSF) for long-term storage of spent fuel from the power units of Rivne, Khmelnytskyi and South-Ukraine NPPs were made. The construction of the CSFSF is under threat because already at the final stage of construction it was decided to liquidate the division of NNEGC “Energoatom”, which was engaged in the construction. Such an incomprehensible decision will not lead to anything positive, but will only delay the commissioning period of the storage facility by 1−2 years. It is shown that the construction of a New Safe Confinement (NSC) over the Shelter object of the Chornobyl NPP is just an intermediate stage in the transformation of the Shelter object into an ecologically safe system. In the near future, it is necessary to perform dismantling of building structures of the Shelter object, the term of operation of which ends in 2023. This is prompted by cases of destruction and collapse of building structures of this object, which occurred last year, and therefore this issue requires immediate solution. The critical state of nuclear science in Ukraine is reflected and it is warned that if the financial support does not change properly, in the coming years the country will be left without a unique scientific institution that conducts research on the safety of nuclear facilities, including the most dangerous in the world Shelter object. Emphasis is placed on the complete absence of a safety culture at the highest level of the country’s leadership, the lack of which is manifested in violations of national norms and international standards, the absence of some leaders in nuclear industry and dangerous enterprises, as well as the attitude of government agencies to the nuclear industry.

Conceptual hydrogeological and numerical groundwater flow modelling around the Moab Khutsong deep gold mine, South Africa.

Prediction of response to fissure water pumping from a shaft on the surrounding areas is conducted with a numerical model, which was refined using environmental stable isotope (ESI), Tritium and hydrochemical datasets. The numerical model domain covers the local carbonate rock units mainly because it is known to be the main source of groundwater.Based on the hydrochemical dataset of the fissure water pumped at the shaft, strong signature of Na–Cl type water originating from the seepage of a waste rock dump as well as polluted water from mine offices, loading/unloading and parking lot areas, is evident. The environmental isotope data demonstrated that fissure water intercepted at the shaft has strong footprint of surface water and polluted groundwater from nearby areas. The 30-year numerical model prediction indicates that pumping at a rate of 2500 m3/day or more would cause the radius of influence to expand to areas where the central tailings storage facility is located and could possibly draw highly acidic water. Interception of acid rock drainage could cause sever corrosion of pump infrastructure, enhance dolomite dissolution and local ground subsidence as well as possibly compromise the structural integrity of the central tailings dam.It is recommended that the current groundwater monitoring network be revised for taking proactive action. The study highlights the relevance of integrating various sets of data to improve understanding of the conceptual flow before any numerical modelling is attempted.

Data Warehouse Testing and Security: A Conspectus

Data warehouse is a central storage facility that stores information from many sources which can be in structured or unstructured format, queries this information for retrieval based on certain input facts and delivers the outcome analysis to many analysts, to meet decision support and business intelligence requirement. Not much research has been carried out in this research area in the past few years. In this research paper, we are discussing the data warehouse architecture and the testing techniques that are used for best suited to be used for the data warehouses. Literature for the testing techniques is integrated at one place and the outcome is to focus on security issues while performing data warehouse testing.

System of special water purification of spent fuel pool of Beloyarskaya Nuclear Power Plant unit BN-800

The problem of handling of nuclear power plants radioactive waste has a significant impact on the development of the nuclear industry. An effective strategy for radioactive nuclear waste should include all of the components and processing steps since waste formation to final disposal, taking into account emergence of new technologies, changes in the regulatory authority requirements, the duration of the time intervals separating the initial and the final stage of the treatment process [1]. After unloading from the reactor core spent fuel assemblies are placed in spent fuel pools for removing of residual heat and radioactivity decrease. After one year of conditioning radioactivity is reduced by about 10 times, after 5 years radioactivity is reduced by 35 times. After 3-5 years the spent fuel assemblies can be transported to a centralized storage facility or sent for processing. However, the maintaining of necessary conditions for temporary storage is an important task that is carried out by special water treatment systems of the spent fuel pool [2]. This article considers the water purification system of the spent fuel pool of the Beloyarskaya nuclear power plant, which is the flagship of Russian nuclear power industry.

CENTRAL STORAGE FACILITY FOR MUSEUM COLLECTIONS: A NEW TASK FOR THE NATIONAL INSTITUTE FOR MUSEUMS AND PUBLIC COLLECTIONS

Museum is collections. Their safe and appropriate storage has always been and will remain the basic statutory activity of every museum. As can be found in both domestic and international sources, merely a fraction of museums’ collections is on permanent display, while their remaining part is kept in museums’ storerooms. Therefore, the priority goal of every museum, of its management, and organizer, should be the availability of an adequate storage area. Regrettably, history and praxis demonstrate that it is precisely within this field that museums have always had and continue having the greatest needs. Worldwide museology faces the ongoing challenge of museum collection storage, and this is the challenge that Polish museums face as well. Fortunately, for over two decades a process of actual transformation in this respect has been occurring, the latter resulting in modern storage facilities being built. These, complying with the latest standards, shall guarantee high-quality protection to the collections, as well as a low-budget construction, and low energy consumption in the course of operations. Poland, too, has been participating in these changes. Recently, the topic of museum storage areas has entered the list of priority tasks of the Ministry of Culture and National Heritage, which in 2016 commissioned the National Institute for Museums and Public Collections (NIMOZ) to provide appropriate reports, analyses, and concepts, while in 2018 it formally assigned the Construction of the Central Storage Facility for Museum Collections Project (CMZM) to NIMOZ. A new position of the Director’s Proxy for the Central Storage Facility for Museum Collections has been created. This means that a major development in the history of Polish museology has taken place: at the Ministry of Culture and National Heritage and its subordinate cultural institution definite steps have formally been taken in order to resolve the problems of museum collection storage in Poland. The assumption has been made that CMZM will be a pilot and model solution that can be followed by subsequent storage facilities for museums in Poland’s other regions.

Disturbance of a natural hydrogeochemical system caused by the construction of a high-level radioactive waste facility: The case study of the central storage facility at Villar de Cañas, Spain

ABSTRACT This paper analyzes the natural hydrogeochemical conditions of the future Central Storage Facility site at Villar de Canas and evaluates the evolution of the system associated with its construction. The characterization of the hydrogeochemical structure of the system is based on a comprehensive field and laboratory survey, which allowed us to define both the distribution of materials and their hydro-chemo-mechanical properties under isothermal conditions. The resulting observations were used to develop a numerical model in a multiphysics environment solver, which was calibrated from the monitoring of the hydraulic head distribution and from detailed geochemical analysis of water samples. The numerical model indicated that the behavior of the system is governed by a very slow underground flow regime and by equilibrium with gypsum and the dissolution of other sulfated phases; these results also suggest that the construction of facilities will not significantly disturb these processes, showing a very small effect of chemistry on the mechanical evolution (vertical displacements).

HSM and backup services at INFN-CNAF

IBM Spectrum Protect (ISP) software, one of the leader solutions in data protection, contributes to the data management infrastructure operated at CNAF, the central computing and storage facility of INFN (Istituto Nazionale di Fisica Nucleare – Italian National Institute for Nuclear Physics). It is used to manage about 55 Petabytes of scientific data produced by LHC (Large Hadron Collider at CERN) and other experiments in which INFN is involved, stored on tape resources as the highest latency storage tier within HSM (Hierarchical Space Management) environment. To accomplish this task, ISP works together with IBM Spectrum Scale (formerly GPFS - General Parallel File System) and GEMSS (Grid Enabled Mass Storage System), an in-house developed software layer that manages migration and recall queues. Moreover, we perform backup/archive operation of main IT services running at CNAF, such as mail servers, configurations, repositories, documents, logs, etc. In this paper we present the current configuration of the HSM infrastructure and the backup and recovery service, with particular attention to issues related to the increasing amount of scientific data to manage, expected for the next years.

Evaluation of ecological resources at operating facilities at contaminated sites: The Department of Energy's Hanford Site as a case study

The U.S. and other developed nations are faced with many contaminated sites remaining from World War II, the Cold War, and abandoned industries, that require remediation and restoration to allow future land uses with minimum acceptable risk to humans and ecological resources. For large Department of Energy (DOE) sites with massive remediation tasks remaining, it is important for managers to be able to assure regulators, Tribal Nations, and the public that human and ecological health are protected. Hanford Site has the largest and most expensive cleanup task within the DOE complex; cleanup will continue beyond 2090. Cleanup involves the use of operating facilities, which also may present a risk to humans or ecological resources. We present a brief description of a methodology to evaluate risks to ecological receptors at the Hanford Site from remaining remediation tasks, and evaluate the risk to ecological resources that operating facilities present currently, during active cleanup of these facilities, and during the post cleanup period. Operating facilities include current, active operations that are located on the site and aid in site cleanup, including both storage and treatment operations. At the Hanford Site, they include waste treatment plants, sludge basins, waste trenches, Central Waste Complex, storage facilities, and disposal facilities, among others. Risk ratings for ecological resources are highest during the remediation phase. Risk ratings for the operating facilities at the Hanford Site range from not discernible to medium currently, from not discernible (ND) to high during active cleanup, and from not discernible to medium following cleanup. The highest ratings are for the Waste Treatment and Immobilization Plant that is being constructed to stabilize radioactive and chemical wastes, and the Liquid Effluent Retention and Treatment Facility that removes and deactivates hazardous contaminants from waste water. Higher ratings in the post-cleanup period are largely due to restoration of ecological resources during cleanup, which increases the potential for injury (if these resources are harmed) because a site will then have higher quality resources after cleanup than it did before. Assessing the value of ecological resources, and determining potential consequences during active remediation and after remediation is essential for compliance with state and federal laws. Understanding the risks to ecological resources from now until clean-up is completed at these facilities is important because of the potential for ecological resources of high value to be degraded, and because cleanup completion is not expected until 2090 or later. The methodology can be applied to any contaminated site requiring a rapid method of assessing potential damages to ecological resources from proposed management actions.

Medicina pod mrtvaško glavo: SS-Lazarett Laibach 1943–1945

Članek je namenjen predstavitvi esesovske vojaške bolnišnice v Ljubljani, ki je bila med letoma 1943 in 1945 edina nemška stalna vojaška bolnišnica na slovenskem ozemlju med drugo svetovno vojno. Poleg tega, da je bila bolnišnica nastanjena v več poslopjih v Ljubljani, je imela izpostave tudi na Bledu. Esesovski vojaški zdravniki so skrbeli za zdravljenje tako nemških vojakov, kot tudi pripadnikov protikomunističnih formacij v nemški službi, ki so delovale na slovenskem ozemlju. V Ljubljani sta poleg vojaške bolnišnice delovala še osrednji laboratorij in osrednje sanitetno skladišče, ki sta pokrivala celotno Jugoslavijo.

Verification and validation of radiation source term capabilities in STREAM

This paper presents the verification and validation of the radiation source term calculation capability implemented in the reactor analysis code STREAM for pressurized water reactor (PWR) spent nuclear fuel (SNF) analysis. Activity, decay heat, neutron and gamma source spectra of irradiated PWR fuel assemblies are calculated with STREAM and ORIGEN and the results obtained are compared. The verification is performed with Westinghouse 15 × 15, 17 × 17 and Combustion Engineering 16 × 16 designs with enrichment of 3–5 wt.% 235U, burnup of 30–60 GWd/t and cooling times of 0.3–1000 years. The radiation source term comparison between STREAM and ORIGEN indicates that the implementation of the source term equations is correct. The validation is done by comparing STREAM calculation results against 91 decay heat calorimetric measurements for 52 PWR fuel assemblies performed at the Swedish central storage facility for spent nuclear fuel, CLAB, and United States Hanford Engineering Development Laboratory (HEDL) and General Electric Morris Operations. The measured fuel assemblies have enrichment of 2–4 wt.% 235U, burnup of 28–51 GWd/t and cooling times of 2–27 years. The comparison between calculated and measured decay heat shows good agreement. For most of the measurements analyzed, the calculated decay heat is within the range of the measurement uncertainty. The average, overall C/E over 71 CLAB decay heat measurements is 1.000 ± 0.017, and 0.997 ± 0.013 for 20 US measurements. Overall, this work demonstrates that STREAM can be reliably used to predict PWR SNF radiation source terms.